JPRS ID: 9851 USSR REPORT ENGINEERING AND EQUIPMENT

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• Sequence Number: 32
• Content Type: REPORTS

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JPRS L/9851
15 July 1981
I~SSR Re ort
p
ENGINEERING AND EQUIPMENT
(FOUO 4/81)
FBIS FOREIGN BROADCAST INFORMATION SERVICE
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_ JPRS L/9851
15 July 1981
USSR REPORT
ENGINEERING AND E~UIPMENT
(FOUO 4/81)
CONTENTS
NUCLEAR ENERGY
Using Vertical Steam-Raising Units to Further Improve
Geaerating Facilitiea With WER Reactora 1
Interaction of Gas Coolant Counterflowa in a Model of Sphere
Charging of the Core of the VG-50 Non-Channel Reactor........... 8
Enlargement of High-Pressure Iieaters for High-Power
GenArating Facilities in Nuclear Electric Plants
With WER Reactors 15
_ Planning and Auilding Nuclear Electric Plante 19
Decontamination of the Equipment in Nuclear Electric Power
Stationa With WER-440 Reactors 21
NON-NUCLEAR ENERGY
Energy-Storing Materials and Their Use 28
- CONSTRUCTION
Continuous-Action Excavators 30
NAVIGATION AND GUIDANCE SYSTEMS
Firing Ground-to-Air Miesiles 33
' FLUID MECHANICS
Operation of Marine Hqdroacoustic Stations 37
- a- [III - USSR - 21.F S&T FOUO]
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MECHANICS OF SOLIDS
Plates and Shella With Discontinuous Parameters.....������~������� 40
Dynamic-Energy Relations of Oscillatory Systems 42
TESTING AND MATERIALS
Erosion Strength of Components of Flightcraft Enginea and
Power Plants 44
Improving the Efficiency of Selective Testing of the Metal
- of Nuclear Electric Power Station Equipment......��������������� 47
_ b _
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NUCLEAR ENERGY
UDC [621..311.25:621.039J:621.181.6
USING VERTICAL STEAM-RAISING UNITS TO FURTHER II~II'ROVE GENERATING FACILITIES WITH
WER REACTORS
Moacow ENERGOMASHINOSTROYENIYE in Russian No 3, Mar 81 pp 2-4
[Article by Candidate of Technical Sciences Yu. V. Kotov, Doctor of Technical
Sciencea N. M. Markov, Candidate of Technical�Sciencea I. K. Terent'yev, engi-
neers L. L. Bachilo, G. Ye. Kelin, candidates of technical sciences A. A~. Piska-
rev, M. I. Grinman and Engineer P. A. Kruglikov]
[Text] One way to improve nuclear electric plants is to increase the initial
steam parameters and optimize the structure of the heating arrangement. For
nuclear electric facilities with WER [water-cooled water moderated power] reac-
tors, without changing the parameters of ::he primary circuit (pressure and tem-
perature of the coolant at reactor inlet and outlet), the parameters of the secon-
dary circuit are determined by the minimum temperature difference in the steam-
raising unit.
In the horizontal steam-raising units that are used for generating facilities
with WER reactora, the entire heating surface worke as an evaporator. The feed
water supplied to the steam chatnber in the ateam-raiaing unit is heated from
temperature t~,,~ (at the outlet from the regenerating aystem of the turbine set)
to the saturation point tei correaponding to the steam presaure by condeneing
- some of the spent eteam. In this case (Fig. 1)
tei ~ t2 - ~tmin+ ~1~
where t2 is the water temperature in the primary circuit at the outlet from the
steam-raising unit; ~t~n is the minimum temperature head at the beginning of the
evaporative section. At the minlmum poesible value of ~t~n ~ 10�C accepted in
the generating units of the WER-1000 the initial ateam preasure of pp = 6.4 MPa
is essentially the limiting value.
In a horizontal steam-raising unit the size of the heating surface is independent
of the temperature of the feed water, and therefore at fixed parameters of the
primary circuit the optimum aize of the heating aurface is determined only by
the relation between the change of electric power of the unit and the heating
surface of the regenerative heaters, i. e. a value of t~ close to the thermo-
dynamic optimum is ~ustified (at ~p = 6.4 MPa, t~ ~225�C). Thus when horizontal
i
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t; c ~
J40
s
310 3 .
J00 ~ . 6 ' ~
teo
_ B
160
1p0
110 ~
!0
100
ll =
~eoo ~ af ~
Fig. 1. t-Q diagram of the ateam-raising unit (Q is the relative thermal power
of the steam-raising unit): 1--saturation temperature t8 corresponding to the
water pressure in the reactor circuit; 2--underheating of water below boiling in
the priraary circuit ~tboil~ 3""parametera of coolant in the primary circuit
t~ = 325�C, t2 = 290�C; 4--minimum temperature difference ~t~,n in an arrangement
without economizer; 5--minimum temperature difference ~t~~n~in a system with
economizer; 6--saturation temperature in the secondary circuit t8i = 286.4�C
(pp = 7.2 Mpa); 7--saturation temperature in the secondary circuit t8I = 278�5�C
(pp = 6.4 MPa); 8--water temperature in the economizer secLion (pp = 6.4 MPa);
~ 9--relative thermal power of the economizer section QeC at pp a 6.4 MPa; 10--
- relative thermal power of the evaporative section QeVBp at pp = 6.4 MPa; 11--
relative thermal power of economizer aection at pp = 7.z MPa; 12--relative thermal
power of the evaporative section QeVB~ at pp ` ~�2 MPa.
steam-raising units are used in WER-1000 generating facilities without changing
the parametera of the primary circuit there is no poasibility of further in-
creasing the parametera of the secondary circuit.
The situation changes when a vertical steam-raiaing unit is used since there is a
capab ility for segregating part of the heating surface in the zone of minimum
temperatures of the coolant in the primary circuit of this ateam-raiaing unit
for the purpose of heating the feed water from t~ to t8i, i. e. introducing an
economizer section QeC >0 (aee Fig. 1).
In this case
t8I ~ t _ t~n+QeC~GI~pi, ~2)
where QeC is the thermal power of the economizer aection, GI and cpI are respec-
tively the flowrate and mean heat capacity of the coolant in the primary circuit
on the economizer section.
2
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Comparing expresaions (1) and (2), we arrive at the conclusion that for unchanged
parameters of the primary circuit and the minimum possible ~t~n, an economizer
section csn raise the pressure in the secondary circuit, and the increase ie
greater ~ith increasing QeC, i. e. decreasing feed water temperature.
When the same presaure is maintained in the secondary circuit of the vertical
steam-raiaing unit as in the horizontal unit the miniminn temperature head iR
greater for the vertical unit, ~t~~n = t3 - tsi > ~t~n, where t3 is the coolant
temperature in the primary circuit corresponding to the minimum temperature dif-
ference in the vertical ateam-raising unit. As a consequence, the mean logarith-
~ic temperr~tu~e head ~tm lo~g~ for the vertical steam-raising unit is higher than
the corresponding logarithmic tEmperature head ~tm io of the horizontal ~init,
which in turn gives a gain in heating surface for thegvertical unit. Calculations
: show that at pp ~6.4 MPa, this gain is an estimated 20% over the heating surface.
However, resesrch has shown that the advantagea of segregating the economizer
sec.*.ion in the vertical steam~-rai~ing unit c~n be put to more effective use for
raising the initial ateam parameters rather than for reducing the area of the
heatin~ surface, as relative reduction of the average temperature Yeead with in-
creasing pressure in the secondary circuit is lower in the case of the vertical
steam-raising unit than for the horizontal unit. Thus as the parameters of the
_ secondary circuit are increased, there is less of an increase in the heating sur-
face of the steam-raising unit with the economizer than without the economizer.
Th.is ratio in the change of heating surfaces increases in favor of the vertical
steam-raising unit if we consider the fact that there is some increase in the
thermal power of the economizer section with increasing tsi, which leads to an
increase in temperature t3.
Thus for constant thermal power of the reactor and parameters of the primary
circuit tl = 325�C and t2 = 290�C, at an initial pressure of pp = 6.4 MPa the mean
logarithmic temperatuz�e difference for a horizontal steam-~raising unit ~tm log
is 24.4�C, while for a vertical steam-raising unit at t~ ^ 220�C and Ot~n of
16.8�C, .
~tm log ' ~t~~logQeC + Otm~~gg4evap ~ 31.5�C,
where QeC and Qevap 8re respectively the percentages of thermal power of the
economizer and evaporative sections under condition of equality of the heat
transfer coeff icients on these sections.
Thus the difference between the heating surfaces of the two types of ateam-
raising units at ppi 6.4 MPa is about 29~.
- As a result of the pressure increase in the secondary circuit to pp= 7.2 MPa,
for the horizontal steam-raising unit at ~t~nin= 4.6�C, ~t 1og = 14�C, whereas for
the vertical unit ~tm log = 23�C, i. e. in this case the d~fference between the
_ heating surfaces will be about 64% in favor of the vertical steam-raising unit.
If we consider some difference in the heat transfer coefficients on the econo-
mizer and evaporative sectiona, the gain in~surface for the vertical unit at
pp ~ 6.4 MPa will be about 20X, and at pp= 7.2 MPa it will be about 45X.
3
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Fig. 2. Change in ad~usted expenditures for a
~Ca, thous. rub/yr WER-1000 generating facility with horizontal
- steam-raising unit as a function of the initial
~ steam pressure: 1--for the steam-raising unit
~ (pCSR); 2--replaced power,for the intermediate
eoo superheater and for the regeneration system
(pCal +OCBH +~Caeg) ; 3--total for the unit (E~Ca)
~oo F
t ' ~Ca, thous. rub/yr
~1oa
a Fig. 3. Change in adjusted i
6p0' a expenditures for a WER-1000 aoo
i ~
generating facility with 4~
~ _ vertical steam-raising uni.t
as a function csf initial o o ~a s p, MPa
-I presaure pp and feed water
~ _ ~ temperature t~,,~: I--t~=180�C; - ~ ?
II--t 200�C; III--t s 220�C; 1--for the steam- -AOo
raising unit (~CSR) ; 2~for replaced power, for ~_~too ?
the intermediate auperheater and for the regener-
ation system (~Cgl + ~CBH + ~Caeg) ; 3--total for the _~600 ~
unit (E~Ca) ~
- zooo
The described situation ia illustrated by a comparison of Fig. 2 and 3 from which
we can see that the rate of change in adjusted expenditures for the steam-raising
unit with increasing pressure is considerably greater for the horizontal steam-
raising unit than for the verti;~l one (difference in slope of the curves for
OCaH) .
The optimum initial pressure is determined from the value of
minE~Ca ~ ~C81 + ~CaH + ~Caeg - ~CBR,
where ~Cal + ~CaH + ~Caeg is th~ total change in adjusted expenses for replaced
- power, for the intermediate superheater and for the regeneration system; ~ CaR
is the change in ad~uated expenditures for the steam-.raising unit.
The optimum value of pp corresponding to minE~Ca for a vertical stea~-raising
unit will always be higher than for a horizontal unit since the curve for ~CaR
with the same behs~vior of thermal economy with increasing pp for the vertical
~ unit lies below the analogous curve for the horizontal unit, and the overall
curve E~Ca changes aign of the derivative at a point corresponding to a higher
value of pp.
These is also a change in the optimum feed water temperature when a horizontal
steam-raising unit is uaed. In the horizontal steam generatur, expenditures had
no effect on the optimum t~. In the vertical unit, the optimum feed water tem-
perature is defined as the minimum difference of reduced expenditures OCal due
- to the change in power of the generati~eg + pC~Hexanddexuenditureahfore~heesteamn
system and intermediate superheater ~Ca a, P
raising unit pCaR.
4
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Fig. 3 showe how the adjusted expenditurea vary by components as a function cf
pressure in the secondary circuit and temperature of the feed water in a r~,nge
of 180-220�C for a WER-1000 generating facility with vertical steam-raising
unit. An increase of initial pressure in the vertical steam-raising unit shifte
the optimum temperature of the feed water tapard lower values.
At currently accepted parameters of the primary circuit for a vertical steam-
raising unit the optimum parameters of the secondary circuit are initial pressure
of 7.2 MPa and t~ = 200�C. These parameters give an appreciable economic effect
as compared with 6.4 MPa and 220�C; they can be obtained by changing the thernnal
arrangement somewhat.
In particular, the optimum feed water temperature (about 200�C) can be obtained
by increasing the pressure in the d~aerator to 1.25 MPa and by feeding the heat-
ing eteam condensate from the single-stage intermediate superheater to the pres-
sure line of the feed pumps.
Implementation of these atepa requires development of a deaerator designed for
increased preasure and the incluaion of an additional pump in the heating syatem
= for transfer of the condensate of the intermediate eteam superheater. However,
these expenditures are paid back with intereat by the advantages that are ob-
tained as compared with the heating system for horizontal ateam-raising units.
Let us liat the most important of these advantagea: feeding the condensate of
the heating ateam from the in:.ern?ediate superheater into the feed water channel
improves the economy of ~~he generating facility by reducing the power of the
feed pump and cutting ].osses in heat exchange; increasing the temperature difference
of the heating and heated steam in the single-stage intermediate superheater
(due to increased initial pressure) r~duces the heating surface as compared with
a two-stage superheater; three high-pressure heating stages with total heating
surface of 15,000 sq. m(six ahells) are eliminated from the heating system;
the temperature difference (t8Z - t~). on all working conditions of the steam-
raising unit remains nearly constant because hot condensate of the intermediate
superheater is fed into the feed water line; the increase in initial parameters
of the secondary circuit improvea the thermal economy of the generating facility
by about 0.71'; the volumetric flowrate of live steam is reduced by about 17Y,
which reduces losses of presaure in the pipelines and the stopping and regulating
equipment~ and givea an additional gain in thermal economy of about 0.2~.
The use of a vertical eteam-raising unit and reconfiguration of the thermal ar-
rangement, when introduced can save more than one million rubles of capital invest-
ments and about 700,000 rubles per year in reduced expenditures, which is equiva-
Ient to a total reduction of specific capital expenditures for the generating
facility with WER reactor of about 4 rubles per kW (table) without consideration
of the reduction of capital investmente in the reactor department (etructural
part).
The use of vertical ateam-raising units is in no way detrimental to the safety
of reactor operation, aince the water reserve in the shell of the steam-raising �
unit is not reduced as compared with the horizontal steam-raising unit.
Thus the use of a vertical ateam-raising unit and the concomiCant implementation
of the enumerated steps considerably aimplifies the heating syatem, improves the
5
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working reliability of equipment, and enables the use of a standardized thermal
arrangement with unified auxiliary equipment for generating facilities with WER-
1000, RBMK-1500 and RBM-KP-2400 reactors. In this system, the following basic
equipment that makea up the turbine set is standardized: steam-generator sepa-
rators, condensate pumps for the intermediate steam superheaters, heaters of
the low-pressure regeneration system, deaerators and turbine feed unita.
COPYRIGHT: Izdatel'stvo "Mashinostroyeniye", "Energomashinostroyeniye", 1981
6610
CSO: 8144/1087
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UDC 621.029:536.24.023.
INTERACTION OF GAS COOLANT COUNTERFLOWS IN A MODEL OF SPHERE CHARGING OF THE
CORE OF THE VG-50 NON-CHANNEL REACTOR
Moscow ENERGOMASHINOSTROYENIYE in Ruasian No 3, Mar 81 pp 2-4
[Article by candidates of technical aciencea R. G. Bogoyavlenskiy, G. V. K~;esno-
pol'skiy and Engineer S.'u. N. Pintelin]
[Abstract] Heat exchange in a aphericgl layer has n~t been as well covered in
the current scientific and technical literature ae heat exchange in tubular sur- ~
faces. The reason for this is that up until the early sixties the spherical
layer was treated as a cap without internal heat release with the purpose of
~ a filter or a recuperator charge.
Pro~ects begun in the sixties on non-channel gas-cooled reactors with spherical
fuel elements served as an impetus to development of research on heat exchange
in a spherical layer at high Reynolds numbers. Some of the research that was
done resulted in relations for the intensity of heat exchange of spheres as a
function of Reynolds number at different volumetric porosities of a spherical
_ charge [Ref. 1, 2].
A typical feature of sphere charging of the core of a gas-cooled'non-channel
reactor is that the volumetric porosity will not be the same throughout the core,
particularly during recharging and in operation on the principles of multiple-
. pass or single-pass travel of the fuel elements through the core when lo~al
stacking may arise at isolated points of the spherical charge from tetraocta-
hedral (with porosity m Q 0,26) to cubic (m ~ 0.476), and thera may also be changes
of porosity at the wall.
In experimental work by Decken [Ref. 3] an investigation was made of the nonuni-
formity of the average heat transfer coefficient in a layer wiCh diameter of
- 20 calibers, and at different points of sphere stacking, including at the wall.
Differences were found to range in limits of �10%.
The pattern of heat exchange is particuYarly complicated in a non-channel core �
in the case where it is necessary to cool spherical fuel elements of the reactor
when part of the gas flow is directed for cooling spherical fuel elements being
unloaded through a discharge channel.
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There a~ce as yet no methods in the scientific and technical literature for calcu-
lating gas flows in spherical packing in the presence of counterflows of differ-
ent intensity.
In the simplest case we can consider the encounter of a main flow of gas coolant
penetrating through the sphere charge of a non-channel core with the gas flow
leaving the unloading channel counter to the main flow. After mixing in the
~ sphere layer, both these flows are removed from the core to the hot gas collec-
tor situated at som~ distance from the walls of the channel for unloading the
spherical fuel elements. It is natural to assume th~ existence of some region
in the charge where the velocities of the flows are mutually cancelled, and con-
~ sequently there is appreciable detriment to heat transfer and an associated ef-
fect of overheating of fuel e].ements that have sufficient heat relEa~e in this
region.
The research plan included getting data on the magtiitude oc heat exchange in
a sphere charge in the region of mixing of counterflows of different intensity.
In addition it was necessary to determine more precisely the dependence of heat
exchange on Reynolds number for the region outside the flow mixing zone. With
consideration of data cited on the posaible variation of porosity through the
core during recharging, recurrent measurements must be made, i. e. they must
be statistical insofar as possible.
The experimental study was done on a VNIIAM atand [expansion not given], which
is a closed circulation loop with gas blower, an experimental section and auxili-
ary heat exchangers (Fig. 1). Provision is made in the loop for separating the
coolant into two streams and feeding them to the experimental sect.ion. Each
of the coolant streams is provided with instrumentation for determining the flow-
- rate, and with choking devices for regulating the flowrate.
Fig. 1. Diagram of stand: 1. sphere duct; 2--tube
. -J~d for feeding spheres into experimentalfsection; 3--mecha-
~ niam for raising the calorimeter unit; 4--calorimeter
~ r unit poaition indicator; 5--calorimeter unit; 6--power
shell; 7--lines to measurement instrumentation; S--
sealed electric entrance; 9--flexible thermoelectrodes;
10--upper cylinder of model with hemispherical displa-
- ,
cers; 11--central chamber of the model; 12--perforate
bottom of the central chamber; 13---lower cylinder of
14
the model; 14--sphere charge of the model; 15--e ec-
~~s ~ ~16 trically driven sliding grate; 16--safety valve; 17--
~ water type gas cooler; LS--compressor; 19--gas.blower;
~B 20--totai stream flow meter; 21--electric gas heater;
22--flowmeter for the counterflow; 23--storage hopper
~1971 r0 '~9
The experimental section is a cutaway model of the reactor core including the
unloading channel. It is made in the form of two coaxial cylinders of different
diameters. The main upper cylinder, 1200 mm high and 580 mm in diameter (13
calibers) is interfaced with the lower cylinder, 405 mm in di'ameter (9 calibers)
by a cylindrical chamber 300 mm high (6.5 calibers) and 850 mm in diameter (19
calibers).
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The lower part of the chamber has a tapered transition to the lower cylinder
without holes to a diameter of 580 mm, and then perforated up to a diameter of
850 mm. Beginning at the perforated section of the chamber bottom is a gas col-
lector that takes the gas out of the model. In the bottom of the lower cylinder
- is an electrically driven sliding grate. The upper and lower cylinders and the
cylindrical chamber are filled with graphite spheres 45 mm in diameter. The
model is filled with the spheres from the top through a tube 50 mm in dia~eter
with lower end dropping below the level of the upper cylinder. The model is
emptied by opening the sliding grate, the spheres dropping into a collector:
an inclined pipe with diameter of 4.5 calibers. To prevent direct leakage of
gas along the upper wall, hemispherical displacers are installed in the upper
cylinder that simulate an infinite laye~.
The main gas flow entera from the power shell that accommodates the pressure-
relieved experimental section. Via the open end of the upper cylinder the gas
flowa downward through the sphere layer and out to the collector through the
perforationa in the tapered bottom of the chamber.
The gas that cools the fuel elements in the unloading channel is fed through
- the sliding grate into the lower channel and moves counter to the main flow,
and then after mixing with the main flow above the unloading channel, this gas
also flows out to the collector.
Located in the sphere layer is a calorimeter unit that can be moved vertically
along the axis of the model (Fig. 2) [photo not reproduced]. The unit is raised
by a special lifting mechanism, and lowered together with the sphere layer when
the spheres are partly unloaded from the model by moving the sliding grate. The
calorimeter unit ie assembled so as to cover the cross section of the model as
completely as possible.
Each calorimeter in the unit is a sphere 45 mm in diameter made up of two cop-
per hemispheras 1 mm thick (Fig. 3) [photo not reproduced]. The hemispheres
are ~oined by a copper core on which a tubular electric heater is installed with
a power of 300-350 W. Welded to the surface of the sphere are three KhA (KTMS)
thermocouples. The free part of the aphere is filled with molten lead to improve
uniformity of distribution of the heat flux over the surface of the calorimeter.
The thermoelectrodes of the thermocouples and the electric leads of the heater
are brought out through a stainless steel tube 16 mm in diameter with wall thick-
~ ness of 1.25 mm connected to the sphere with solid solder. This tube holds the
calorimeter in the unit. On the other end of the tube is a terminal block through
which all electrodes are connected by flexible leads to the sealed entrance from
the power shell, and thence to the measurement instrumentation and power trans-
formera. ~
To prevent gas leakage along the calorimeter holder tube, on the outside are
ten freely moving drilled graphite spheres of the same diameter as the charge
(45 mm). The locaCion of the calorimeter unit in the layer is shown by a special
indicator that can be observed on the outside of the shell. Connected in the
section of the tube for feeding the counterflow is an electric heater for raising
the gas temperature by 20-30�C over the unheated main flow.
10
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The measurements made in the experiments included gas pressure in the shell,
flowrate and temperature of the main flow and couterflow, temperature of the
_ gas flowing around the calorimeters, temperature of the walls and power of the
calorimeter heaters. The experiments were done under conditions of stabilization
of flowrates, pressures and temperatures of both airflows, and the temperature
of the calorimeters. Temperature stability was monitored from the readings of
an EPP-09 automatic chart-recording ~:at~ntiometer.
The first distinguishing feature of these experiments was measurement of the
temperature of the gas impinging on the calorimeter and the temperature of the
calorimeter wall by the same thermocouplea installed on the surface of the sphere
- with the heatera of the calorimeter disengaged and engaged respectively. The
second feature is lowering of the calorimetera together with the layer of spheres,
- which enabled measurement with the same calorimeters at different points height-
wise of the layer. The features give a more reliable picture relative to the
distribution of gas temperature and intensity of heat exchange in the volume
of the aphere charge where the calorimeters are located.
The experiments were done in two series. In the first series an investigation
was made of the way that the intenaity of convective heat exchange depends on
_ Reynolds number for the spheres located in the layer under conditions of unidirec-
tional flow. Experiments of this series were done with the calorimeter unit
in the upper position and with feed of only the main airflow at different flow-
rates. The resultant experimental data in the form of the Nusselt number (Nu)
as a function of Reynolds number Re (Fig.
Nu 4) calculated with respect to gas velocity
� in the full cross section without consider-
doo ation of blocking of the channel by spheri-
~oo
soo cal elements, and with respect to the diam-
soo eter of a sphere as a characteristic dimen-
voo 1 sion show that over a range of Reynolds num-
bers of 3�103-20�103 with error of 15% we
roo can use the formula
,
?oo - Nu = 0. BReo ~ 6 5~
,so - -
and for Reynolda numbers of 20�103-50�103
- with error of 7~L we can use the formula
r00; 4 S~~ q.q IO 15 ?0 70 40 Itt10~~
Nu = 0.48Re��~.
. Fig. 4. Relation Nu = f(Re) in the
.case of unidirectional flow: 1-- The indicated errors are determined mainly
_ Nu = 0.8Reo,65~ 2__Nu = 0.48Re~�~ by nonuniformity of the distribution of heat
transfer intensity in the sphere packing
crosa section
The experiments of the second series were done with lowering of the calorimeter
unit from the upper poaition to the mouth of the channel for unloading the
spheres. This arrangement included feed of both the main (upper) gas flow, and
the (lower) counterflow via the unloading channel. The main flow was the "cold"
' gas, and the counterflow had a temperature 20-30�C higher than the main flow.
11
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- The wall temperature of the calorim-
etere on each of the levels heightwise H~Sph ,
over the mouth of the unloading chan- 'p s
nel was measured first wit~hout engage-. p
ment of the heaters (to determine the � j
temperature of the air flowing over
the calorimeter). Then the heaters ?
of the calorimeters were energized and Q5 ~ :
~o
after stabilization had been reached o� '
(the calorimeters were heated), repeat a)' ~
measurements were made of the emf of o
the calorimeter tt~ern?ocouples.
3~
These emf's were used to determine wall t
temperature, which in combination with ~
measurement of electric power and with ~ ~
conaideration of thermal loseea as a b~
result of heat tranafer to ad~acent ~ ~
unheated spheres enabled determination 6.
of the heat transfer c~efficient, and p s
_ consequently the Reynolds number for
each of the calorimeters. 4
~
The calorimeters were lowered together as
with the spheres of the layer as some ~ ~ ~
of the spheres were discharged through
the unloading channel. The experiments 6 5 r~+ S ~ 6�6O.
with lowering of the calorimeters were R/daph�
done at only one maes velocity of the
main flow (in the upper cylinder). The Fig 5. Diagram of mixing of main
mass velocity of the counterflow Wa8 flow and counterflow in the form of
_ measured over a wide range (from 50 the relation (to- t)/(tp- tcf~ ~
to 125% of the mass velocity of the
main flow, nominal velue of 75~). f(H/dsph; R/ds h) at different ratios
of the mass ve~ocities of the main
In the experiments of thia series one flow and counterflow; a--0.5; b--
can determine the course of mixing of 0.75; c--1.25
the main flow and the counterflow, and using the temperature field
delineate the so-called "mixing zone" [Ref. 4] by
of the gas in the layer as determined from measurements without heating of the
calorimeters. The mixing zone is that part of the volume of the sphere layer
above the mouth of the unloading channel where the flow over the apherical fuel
elements in each elementary volume consists partly of the gae of the main flow
(arriving from above) and partly of the gas arriving from below (from the unload-
ing channel)� remervaluesfoccureareetherboundari s for~theOmixingtzoneurfacea
where these ext
It can be seen from the grapha of Fig. 5 that the position of isotherms in the
form of relations (to- C)/(to- tcf~ � f(H/dePh; R/d8ph) that reflect equal de-
grees of mixing of the main flow and counterflow changes with a change in the
ratio of their mass velocitiea.
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The mixing zone increases with ar. increase
T ~ T T/d~ph in the mass velocity of the counterflow.
Beaides, the region of the mixing zone
� where intermixing of the flows takes place
o s most intensively, i. e. where the iso-
~ therma are moat densely spaced, shifts
Q~ j up noticeably (by nearly 1~ sphere cali-
? bers) with increased mass velocity of
4~ the counterflow as compared with nominal
4f ' conditiona. At the same time, there is
~ ~ an increase in the overall height of the
, a mixing zone, especially on the edges,
~ where the gas velocity at the wall ia
' 6 considerably greater than the average
s due to a~ump along the wall of the un-
loading channel. Errors in placement
qe 4 of the isotherms due to reduction of the
Q~ ~ temperature of the counterflow caused
pQ ? by heat losses through the wall of the
o Q4 ~ central chamber do not exceed 5X.
D
) The experiments of the second aeries also
~.0 ~ enable us to single out the "zone of im-
~ paired heat exchange" which is the part
6 of the volume of the sphere layer above
9 S the unloading channel where we observe
_ q a reduction in the intensity of heat ex-
3 change as compared with the overlqing
sphere layer due to a reduction in the
- Q.s ? mean velocity at which the coolant flows
Q~ ~ over the spherical fuel elements, which
s s ~ ~ ~ ~ R~ ia cauaed by the interaction of the op-
R/deph c) poaed flows in combination with a change
in the direction of flow determined by
Fig. 6. Diagram of distribution of the configuration of the walls of the
heat exchange intensity above the funnel and ~he location of the point where
mouth of the unloading channel the coolant leaves the model of the reac-
Nu/Nuo= ~(H/dsph; R/dsph) for dif- tor core.
ferent ratios of the mass veloci-
ties of the counterflow and the Fig. 6 shows graphs of the distribution
main flow: a--0.5; b--0.75; c--1.25 of linea of equal intensity af heat ex-
change Nu/Nuo m~(H/d8ph; R/dsph) plotted
in the scale of the average Nusselt number (Nuo) in the aphere layer above the
_ zone of mixing of the flows and the zone of impaired heat exchange. It is clear
from theae diagrams that the minimum relative valuea of the Nuaselt number are
0.4-0.45, and are situated at low velocities of the counterflow close to the
mouth of the unloading channel. When the masa velocity of the counterflow is
increased, the region with minimum Nusaelt number (0.5) "floate" upward nearly
two calibera above the mouth of the channel, and ite volume decreases consid-
erably.
13
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There is a noticeable correlation between the diagrame of mixing and heat ex-
change, eapecially at high velocities of the counterflow, with respect to non-
uniform distribution of velocities in the unloading channel. Therefore it is
of interest to study the inside of the unloading channel. The form of the dia-
a grams may also be considerably influenced by poir_ts of location of coolant dis-
~harge.
~ Our research enabled qualitative investigation of one of the possible ways of
controlling the zone of impaired heat exchange close to the mouth of the channel
for unloading fuel elements from the reactor core by altering the ratio of mass
velocities of the main flow and counterflow. In doing this, we have established
that for the investigated model and designs geometrically similar to it, doubling
the mass velocity in the unloading channel (as compared with the nominal value)
increasea the minimum intensity of heat exchange, reduces the volume where it
occurs, and reduces the temperature of the coolant flowing over the fuel elements
in the zone with impaired heat exchange conditions. This reduces the danger
of exceeding the permissible fuel element temperature and improves conditions
- of heat exchange on the approach to the unloading channel where cooling is to
tkae place.
REFERENCES
1. Bogoyavlenakiy, R. G., "Gidrodinamika i teploobmen v vysokotemperaturnykh
yadernykh reaktorakh s sharovymi tvelami" [Hydrodynamics and Heat Exchange
in High-Temperature Nuclear Reactors With Spherical Fuel Elements], Moscow,
Atomizdat, 1978, 112 pages.
2. Bogoyavlenskiy, R. G., "Hydr.odynamics and Heat Exchange in High-Temperature
Reactors With Spherical and Prismatic Fuel Elements (Survey)" in: "Voprosy
atomnoy nauki i tekhniki" [Problems of Nuclear Science and Engineering],
Moacow, Institute of Nuclear Energy imeni I. V. Kurchatov, 1977, p 67 (Series
on Atomic-Hydrogen Power, No 2(3)).
3. Decken, G. B., Hautke, A. I., Binckenbanck, I. and Backus, F. P., "Bestimmung
der W~rmeubergang von Kugelschuttungen in durchstrtimendea Gas mit Hilfe der
Stofftlbergang", ANALOGIE. - CHEM. - INGR. - TECHN., 1960, B. 32, s. 591.
4. "Current State and Outlook for Development of the HTGR in the USSR" in:
"Atomno-vodorodnaya energetika i tekhnologiya" [Atomic-Hydrogen Power and
Technology], edited by V. A. Legaeov, Moacow, Atomizdat, 1979, No 2, pp 57-66.
COPYRIGHT: Izdatel'stvo "Mashinoetroyeniye". "Energomashinostroyeniye", 1981
6610
CSO: 8144/1087
14
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UDC [621.311.25:621.039]:621.182.14-11.001.2
ENLARGEMENT OF HIGH-PRESSURE HEATERS FOR AIGH-POWER GENERATING FACILITIES IN
NUCLEAR ELECTRIC PLANTS WT''~ VVER REACTORS
Moecow ELEKTRICHESKIYE STANTSII in Rusaian No 2, Feb 81 pp 12--13
- [Article by candidates of technical sciences V. M. Marushkin, Ya. L. Polynovskiy
and G. T. Shkol'nik, Ural Affiliate of the All-Union Scientific Research Insti- ~
tute of Heat Engineering imeni F. E. Dzerzhinakiy)
[Text] A characteristic feature of the current stage of nuclear power develop-
ment is an increase in unit capacities of facilities made in the form of indi-
vidual generating units including a reactor, steam generators and a turbine. It
is quite natural to expect that the effect of this trend would be maximized by
enlarging all types af equipment in the electric power plant.
However, the enlargement of certain kinds of equipment presents rather complicated
problems. This applies in particular to high-pressure heaters. Difficulties in
enlargement of such heatera are due to high flowrates o�f the feed water at the
same time that water velocity is reatricted to.leas than 2 m/s in the elements of
the heating surface; another source of problema involves limitations on overall
dimensiona of the heaters. The water velocity constraint is a result of technical
and economic factors, and also the limita of reaistance of heater coils to cor-
rosion and eroaion, as operating conditione permit the use of relatively inexpen-
- sive grade 20 eteel for making high-preeaure heating coile for generating facili-
tiea with VVER [water-cooled water-moderated power] reactors.
The 220 MW generating units now being used in nuclear electric plants with WER
reactors according to All-Un~on Standard OST 24.271.28-74 [Ref. 1] are equipped
with PV-1600-92 vertical collector heaters designed by Krasnyy Kotel'shchik Pro-
duction Asaociation. The heater shell has 2600 mm inside diameter and a height
of 10.6 m. .
Having reached the limit with respect to capabilities for further enlargement in
the design featurea incorporated into the PV-1600-92, Krasnyy Kotel'shchik tried
making horizontal high-presaure heaters of chamber type [Ref. 1] in developing
heaters for the fifth generating unit of Novovoronezhsk Nuclear Electric Plant
with two K-500-1500 turbines. However, for technological reasons these heaters
could be made only from austenitic ateel even though working conditions did not
require it.
The coet of a set of auch heaters per 500 MW turbine unit was 2.4 million rubles
(specific cost of 400 rubles per aq. m). Deapite this high price tag, the
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optimum temperature of the feed water accordihenttheglivefeteam paraII?eoers are a
single-pase steam generator with economizer w
7 MPa (70 kgf/cm~) and 310�C. By contrast, Ref. 2 points out that the optimum
' temperature of the feed water would be about 220�C when uaii~ng a~8nnualure
heater with heating surface coating 100 rublea per sq. m, 8
savings of about 150,000 rubles.
~ According to our own analysis, this temperature could be attained by using PV
vertical collector high-pressure heatere based on the PV-2300-380 units currently
installed in the generating units of 500 MW fossil-fuel electric plants jRef. 3].
The feed water in such hi gh-presaure heaters can be heated to 220�C when the pipe
system ia made up of colle ctors w ith diameter of 377 x 24 ~n, and the.flat coils
are formed from tubing w ith diameter of 32x 4 or 32~ in�an arrangement withntwoe .
diameter of the shell of 3200 mm and height of 14
. high-preasure heater etg8e8d suhe~rheate r beingffed~intoathetwaterhfeednline8te
from the water separator an p
A cost
Krasnyy Kotel'shchik ie nearly ready to etart manufacturing auch heatera.
analysis by the All-Union State Institute for the Deeign and Planning of Elec-
trical Equipment for HesonEofideliverylandaiastallation willacosts500~000 rubles
heaters with coneiderati
_ (apecific coat of 120 rub les per eq. m)�
Such heaters in a two-channel model and Wiunithofetheal000eMWiSouth Ukxainianr
~ have now been accepted for the generating ased a h.eatix?g
Nuclear Electric Plant. A number of organizations have prop
arrangemenC with 1.2 ~a ~12 kenerationeaystem~and aa aux liarypPND85xlowepressure
stage in the high-pressure reg
heater for generating units of thia same power.
We feel that this idea is not 88 ea~or aeince witheequalieconomyaand capitalgh
pressure heater with 0.7 MPa deaer ~
outlay it requires development of auYeeof1200�C~ the 1.2 MPa deaerator, and a
feed pump with inlet water temperat
Research projecte done in receof HeateEngineering1lmeni1F8tE.~Dzerzhinakiyion
Scientific Reaearch Inetitute
Krasnyy Kotel'ahchik Pro duction Association [Ref. 4] and the acientific Boiler
tion asaociation of the CeitiallScPolzunov indicate theifeasib ilitynofgconsider_
and Turbine Inatitute imen
ably reducing metal inputs and e8me~81Within acceptableboveralledimensionsVforP
ing two-channel high pressure h
2000 MW generating units. Judgie$8tin unita4oftfoaeil~fuel.yand nuclear elec-
high-preseure heaters in tha gen S
tric facilities ia to sw itch to makx38~ for1riuGlearbelectricaplants)rface from
small-diameter tubing (20 x 3 or 22
The following results are achleved by designing the high~pressure heatera of
high-power generating unita in nuclear electric plan~essurenheatersnofntheigener~
featurea suggested in Ref. 4 for single-shell high-p
ating unite in 800 MW fossil-fuel electric plants. Vertical single-channel PV
16
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Fig. 1. Structural diagram of a eingle-
' channel PV collector high-pressure heater
for generating units of a 1000 MW nuclear ~
~T~ electric facility
. collector high-pressure heaters can be made for 1000
MW generating units in a shell 3200 ~n in diameter and
~ 14.5 m high (Fig. 1) with heat-engineering character-
istics ensuring attainment of a feed water temperature
. of 200�C with two-atage heating and 0.7 MPa deaerator.
The 4000 aq. m heating surface in these h1.gh-pressure
heaters consista of a built-in condensate cooler and
~ a single-pasa condensation zone, and by analogy with
~ the recommendatione of Ref. 4 it is made up of aections
~ in the form of two~double-tube flat coils placed one
over the other and formed from gxade 20 steel tubing
with diameter of 22 x 3 mm welded to intermediate ele-
ments with diameter of 45 x 5 mm. The aections, as
reco~mnended in Ref. 4, are welded to the collector in
two etaggered rows; the atep to each row is 104 mm,
' and the average apacing between coils heightwise of
the high-pressure heater is 26 mm. The collectora are
made of tubing with diameter of 377 x 24 mm.
In this arrangement, the maximum velocity of the water
' in the coils will be lesa than 2 m/s, while that in
the collectore will be about 6 m/s. The maximum
length of the tubing in a coil will be 13 m, and the
high-presau~e heater will mass 250 metric tons. The
~ estimated coat of a single heater is 350,000 rublea.
, _ ~
.
Fig. 2. Structural diagram of a .
doubled eingle-channel chamber ~
high-preasure heater for gener- ,
ating unite of a 1000 MW nuclear
electric plant �
Even greater capabilities for enlargement of high- ~
pressure heaters open up with the acquisition of
chamber heaters. A posaible deaign of a single-channel ~ - ~
chamber high-pressure heater for a 1000 MW generating
_ facility ia shown in Fig. 2.
. When U-tubes with diameter of 16 x 2 mm and length of
10 m are used for the elements of the heating surface
in such a heater with total heating surface of 4000
sq. m, it can be made with a shell diameter of 2000 mm
and length of about 12 m. The grade 20 ateel tube
pl~i:e is 300 ~n thick. The heater maeaes 180 metric tons.
17
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REFERENCES
1. OST 24.271.28074. "Regenerative Heaters for Turbines in Nuclear Electrtc
Plants", Leningrad, Central Scientific Research Design and Planning Boiler
and Turbine Institute imeni L. I. Polzunov [TsKTI[, 1976.
2. Andreyev, P. A., Grinman, M. N. and Smolkin, Yu. V., "Optimizatsiya teplo-
energeticheskogo oborudovaniya AES" [Optimizing Heat Engineering Equipment
of Nuclear Electric Facilities], Moscow, Atomizdat, 1975.
3. "Kotal'nyye i turbinnyye ustanovki energoblokov moshchnost'yu 500 i 800 MVt.
Sozdaniye i osvoyeniye" [Boiler and Turbine Facilities for Generating Units
with Power of 500 and 800 MW. Development and Production], Moscow, Energiya,
19 79 .
4. Polynovskiy, Ya. L., Marushkin, V. M., Kul'mukhametov, T. Ya. et al., "Odno-
korpuenyye podogrevateli vysokogo davleniya dlya energobloka 800 MVt" [Single-
Shell High-Preseure Heaters for 800 MW Generating Unit], ELEKTRICHESKIYE
STANTSII, No 9, 1977.
COPYRIGHT: Energoizdat, "Elektricheskiye stantsii", 1981
6610
CSO: 8144/0820-B
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uDC 62i.o39.5 ~
PLANNING AND BUILDING NUCLEAR ELECTRIC PLANTS ~
Moscow OSOBENNOSTI PROYEKTIROVANIYA I SUORUZHENIYA AES in Russian 1980 (signed to
press 4 Dec 80) pp 2, 188
[Annotation and table of contents from book "Particulars of the Planning and
Construction of Nuclear Electric Plants", by Leonid Mikhaylovich Voronin,
Atomizdat, 4000 copies, 192 pages]
jText] The book discusses the ma~or problems that come up in working out plans
for nuclear electric facilities with different kinds of reactors. Methods and
stages of construction and installa~ian on the faciiity are exa.mined. The ma3or
emphasis is on questions of features that are inherent only to nuclear electric
_ plants. A central place is given to questions of ensuring hig~ quality of the
building, assembly and installation ,jobs, which is especially important for re-
liable operation of nuclear electric facilities. The material is based on ex-
perience in the planning, construction and operation of Soviet nuclear electric .
plants with water-water and channel reactors.
For specialists in the field of~planning, building and using nuclear electric
facilities. Mey be of use to students ma~oring in the appropriate fields in
engineering colleges. Tables 15, figures 73, references 53.
Contents
Preface 3
Introduction
Chapter l. Problems of Safety in the Planning, Construction and Operation
~f Nuclear Electric Facilities 6
1.1. Specific conditions and peculiarities of nuclear plant operation 6
1.2. Nuclear and radiation safety 13
1.3. Safety criteria, and requirements to be met by the nuclear plant on
stages of planning, construction and operation 15
1.4. Ehvironmental impact of plant operation 25
1.5. Steps to ensure safety of nuclear facilities 29
Chapter 2. Planning the Nuclear Electric Facility 36
2.1. Peculiarities and principles of planning nuclear facilities 36
2.2. Meeting safety requirements in planning nuclear electric plants 43
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2.3. Site selection for construction of nuclear facilities ~+5
2.4. Plannin~ of structures and systems for assembly, handling and storage
of radioactive components of equipment, spent fuel, and radioactive
wastes of the nuclear electric facility ~+8
2.5. Selecting the ma~or equipment of the nuclear facility 58
2.6. Particulars and principles of arrangement of the buildings and struc-
tures of the nuclear facility 67
2.7. Configurations of nuclear electric facilities in the USSR 72
2.8. Engineering plan of the nuclear electric plant, its components and
specific features 87
2.9. Ways to improve plans for nuclear electric plants 89 .
Chapter 3. Construction of the Nuclear Electric Facility 95
3.1. Particulars of construction and installation jobs on the nuclear facility 95
3.2. Organizing and planning construction and installation work on the nuclear
electric plant 100
� 3�3� Technolot;ical sequence and combination of construction and installation
work on the nuclear electric plant 111
3.4. f'rincipal methods a.nd stages of installing equipment on nuclear electric
facilities with different kinds of reactors 115
3.5. Specific features in organizing quality control in constructing a nuclear
electric plant 149
3.6. Weldin~, requirements on nuclear facilities 152
3.7. Ins~~ection and qutility control of welds in the installation of equip-
ment on t~ nuclear facility � 154
3.8. Procedure and particulars of tests and certification of installed
equipment on the nuclear facility 157
3�9� Ways to improve efficiency in constructing nuclear plants 160
Chapter 4. Startup and Ad~ustment Work on the Nuclear Electric Plant 163
4.1. Specific features of startup an d ad,justment work on r:uclear plants 163
4.2. Principal stages, content and sequence of startup and ad~ustment work
on the nuclear facility 161+
4.3� Organization of startup and ad~ustment work on the nuclear plant 181
References 183
Alphabetic sub,ject index 186
COPYRIGHT: Atomizdat, ly8o
6610
cso: 1861/98
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UDC [621.311.25:621.039]:576.8.097.37.002.5
DECONTAMINATION OF THE EQUIYMENT IN NUCLEAR ELECTRIC POWER STATIONS WITH
VVER-440 R~ACTORS
Moscow ELEKTRICHESKIYE STANTSII in Russian r;o 4, Apr 81 pp 6-8
[Article by Yu.V. Balaban-Irmenin, candidate of the engineering sciences and
A.L. Teplitskiy, engineer, All-Union Thermal Engineering Institute]
~ [Text] The long-term operation of AES equipment leads to the constant accumula-
. tion of radioactive contaminants on the internal surface of the radioactive loops
of AES's, as well as on the outer surfacesof equipment and walls (floors,
ceilings) of rooms. This process can occur at different rates depending on the
AES technology, the application of various preventive measures, etc., but in any
case, there is an increase in the gamma radiation level fran the AES enuipment
with time, which coniplicates and increases the cost of its repair and metal
monitoring, and in a number of cases, even prevents normal operation of the
electric power station. For this reason, it is necessary to periodically de-
contaminate, i.e., remave radioactive contaminants fram equipment and room
surfaces.
An analysis of the radiation exposure of personnel at AES's shows that the
personnel dosage expenditures are primarily related to equipment repair [1, 2]
and at the present time, the radiation exposure of personnel is 70 to 90 percent
governed by the radioactive contamination of the internal surfaces of the
primary loop equipment, which comes in direct contact with the coolant.
Various methods of removing radioactive contaminants can be used at AES's
depending on the decontamination purposes and facilities: chemical, electro-
chemical, chemical-mechanical and others [3].
The primary method which makes it possible to curtail the dosage expenditures
of AE9 p~rsonnel both during a repair period and in a decontamination period is
the decontamination of the loop equipment while assembled. The traditional,
so-called two bath method is usually used ab.road for this operation, which
consists in the sequential flushing of the primary loop first with a rather
concentrated solution of alkaline permanganate and then with an acid solution
(predaminantly oxalic) with an intermediate flushing with condensate. The
_ 21
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complex configuration of the primary loop and the necessity of careful removal
of the resiudes of the decontaminating solutions fr an it in this case produce
a large amount of radioactive water (up to 70 times the volume of the decontami-
nation loop) and require considerable expenditures of time, which have a direct
inf luence on the duration of the power generator downtime [4]. For this reason,
the primary loop is rarely decontaminated using the two bath method.
Soviet specialists, in con~unction with specialists fr an the GDR, have developed
a new technology for primary loop decontamination. The dissolution of the oxide
film, including radionuclides, is accomYlished in this case by successive
exposure of the f ilm to a solution of potassi~n permanganate and aii etching
solution made of ethylenedi~aminetetraacetic and citric acids. The first test
of the new technology was made in 1978 during the decontamination of the primary
loop of a standard power unit with a WER-440 reactor [5].
The reactor vessel and the volume compensator, which are made of nonalloy steels,
as well as three loops (of ~ix) with steam generators were decontaminated. The
- core was unloaded for the purpose of providing for the insp�ction of the reactor
vessel. The duration of the 3econtamination was 54 hours. Some 84 hours was
expended on the preparatory work. All of the operations were performed with
regular equipment, without the installation of additional hardware.
Some 605 Ci were removed fram the loop as a result of the decontamination,
including 28 percent fissdon products while the remainder were corrosion products.
The following were removed through the dissolution of the oxide films from the
metal surfaces: 86.5 kg of iron, 7.3 kg of chromium and 6.3 kg of nickel. The
reduction in the dosage expenditures of the personnel as a result of the decon-
tamination was governed not only by the reduction in the level of the gamma
radiation doses from the equipment (the decontamination factor reached 25 for
the steam generators), but also by the reduction c~f the time needed~to prepare
the metal for testing, by virtue of removing the oxide film during the decon-
tamination. No corrosion damage to the equipment or traces of secondary
corrosion following the decontamination was detected.
One of the advantages of this technology is the small amount of waste. The
quantity of primary wastes was a total of three times greater than the loop
volume; the volume of concentrated waste amounted to 17 m3.
At the present time, the technology described here has been used to decontaminate
the primary loop of two power units with WER-440 reactors. The results of the
trial have shown that the application of this method can be permitted five times
for the decontamination of one power unit without the danger of corrosion to the
equipment.
In the case of short term shutdowns of power units and a limited amount of
repair and metal testing, decontamination of the entire primary loop is not
expedient. For this reason, independent decontamination systems are widely used
at AES's for individual components of the core loop. Independent decontamination
makes it possible to clean that equipment which requires an increased amount of
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inspection and monitoring work, as well ae to employ the most efficient solutions
in the least amount and the corresponding minimal quanCity of waste.
Figure 1. Configuration of
the decontamina-
~ t ion unit f or the
main circulation
1! pumps .
~ Key: 1,2. Tanks for prepar-
3 y ~ Z ing the solutions;
3. Decontamination
bath for the removed
portion of the MCP;
~ 4. Decontamination
' bath for the rotor
6 of the MCP;
5. Circulation pump;
8 6. Tank for the
~ ~ -~9 hydrogen peroxide
f
f0 ~ solution;
7. Pump for the
5 hydrogen peroxide
solution;
8. Steam feed;
9, Compressed air
feed;
- 10. Condensate drain;
11. Condensate feed.
The main circulation pump (GTsN) [MCP] is that component of the primary loop
which is most often sub,jected to inspection and repair. To decontaminate it,
special decontamination units have been created at AES's, which included [6]:
storage tanks for the workir.g acid and alkaline solutions; a decontamination bath
for the removed portion of t~he MCP; a decontamination bath for the rotor of the
MCP; a solution circulation, feed and return pump; and a control panel (Figure 1).
The outside portion of the MCP is delivered through easily removable covers in
the central room to the decontamination unit and is installed in a special
- bath. The construction of the bath makes it possible to treat only the lower
most contaminated portion of the MCP, which has come in direct contact with the
coolant. Ta decontuminate the MCP rotor, a special bath is also set up, where
to avoid deformation, the rotor is decontaminated in a suspended position.
The solutions are prepared in tanks; thE solutions are fed to the bath��with
the equipment by means of a pump. The solutions are heated up to the requisite
temperature in a heat exchanger, where the temperature of the solutions is
registered by a thermocouple and the readings are fed out on the control board.
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. 6 5
3 5 7
i
~
B ;
1 2
~ 4 ,
Figure 2. ~
~'igure 2. Configuration for the decontamination of the
steam generators.
Key: 1. Cold header of the steam generator;
2. Hot header of the steam generator;
3. Pump;
Blank flange;
- 5. Water feed;
6. Compressed air feed;
7. Tank for the preparation of the solutions;
8. Discharge to the special sewerage system.
The decontaminating solution is circulated by means of the same pnmp. To achieve
the greatest intermixing rate, compressed air is fed into the baths. The framework
of the unit provides for washing the entire system with pure condensate, as well
as repeated use of the solutions. If a chemical reagent does not reach its
saturation after the decontamination cycle is campleted (something which is
determined by analysis), it is expedient to repeat its application, and this
reagent is pumped into storage tanks for the decontaminating solutions.
The structural design of the decontamination baths makes it possible to treat not
only the removed portions of the MCP, but also other small equipment and parts.
A basket which is placed in the large bath is used for this purpose. The
equipment to be decontaminated is loaded into the basket. The usually attainable
decontamination coeff icients f luctuate fram 10 to 100.
A rather typical case of independent decontamination of equipment when assembled
is the decontamination of the steam generators for the WER-440, the sche~matic
of which is ahown in Figure 2[7].
The following equipment was assembled to create this configuration: blank flanges
in the pipe where Du~= 500 mm on the side of the main circulation pump, which
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prevent the decontaminaCing solution getting into the piping; flanges on the
header of the steam generators to introduce and circulate the decontaminating
solutions; a tank with a capacity of 2 m3 to prepare the solutions (at the same
Cime, this tank was used as a"breather"); a pump with a delivery of 45 m3/hr.
The decontaminating solutions were preheated on the side of the steam feed
secondary loop (a pressure of 8 to 12 kgf/cm2) from the turbine room into the
continuous purging line of the steam generators.
TABLE
Concentration, g/1
Temp- A1- Ox- Iron Overall activity
era- kali alic with respect to
Operation ture PH acid the dry residue,
�C Ci/1
Alkalization
(first
cycle) 70 13.21 16 - - 1.4 � 10-5
~ Acid stage
(first
_ cycle) 80 1.11 - 25.2 0.325 2.0 � 10-3
Alkalization
(second
cycle) 80 13.20 10.4 - - 6.2 � 10-6
Acid stage
(second
cycle) 72 1.31 - 21.0 0.230 3.1 � 10-5
Flushing with
a weak
solution
of nitric
acid 78 1.76 - - 0.125 4.2 � 10-6
Note: The concentration of the potassium permanganate during alkalization
was equal to 3 g/1 and the nitric acid concentration during the
etching was 0.3 to 1 g/1.
The decontamination technology included treatment with an alkaline solution
(KOH at 30 g/kg and KMnOq at 3 g/kg) for the case of solution circulation and
a temperature of up to 90 �C (the alkalization was carried out simultaneously
with the warming-up of the steam generator). Then, after flushing with water,
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a treatment was made with a solution of oxalic (IS g/kg) and nitric (1 g/kg)
acids. The final flushing was accomplished with a slightly alkaline water
(2 g/kg KOH), and then with pure water, the decontamination coefficient was equal
to 8. 5.
One of the major reasons for the relatively low decontamination coefficients in
this case is obviously the low liquid velocities. For this reason, the All-Union
Institute of Thermal Engineering imerii F.E. Dzerzhinskiy and the Kol'skaya AES
proposed a special device which makes it possible to produce a liquid mass rate
of flow through the steam generator of a WER-440 reactor of about 1,600 m3/hr
when the pipes where Du = 500 mm are cut off from the steam generators.
A two bath method was used in the decnntamination (see the Table). Just as in
the variant described here, the solutions were warmed up at the secondary loop
side.
As a result o� the first decontamination cycle, 6.685 kg of iron oxides, refigured
for Fe203, were washed out in dissolved form and radioactive nuclides amounting
to 11.16 Ci were removed. An examination of the headers showed that the surface
of. the cold header wa~ completely cleaned of the oxide film; 70 percent of the hot
header surface was coated with a gray colored oxide film. The gamma radiation
dose in the collectors was reduced by a factor 9T10.
The second decontamination cycle was carried out using the same technologp as
the first cycle. Additionally, following the acid:~stage, a weak solution of
nictric acid (0.7 g/1) was used as a rinse. The duration of the second cycle
16.5 hours.
As a result of the second decontamination cycle, 5.2 kg of iron oxides, ref igured
for Fe202, were washed out of the steam generators in dissolved form and radio-
active nuclides amounting to 1.78 Ci were removed. The examination of the headers
after the second decontamination cycle showed that the surface of the hot header
was likewise fully cleaned of the oxide fi1m.
After the second cycle and the disassembly of the device, the Du = 500 mm piping
along with the steam generators were flushed with condensate.
The gamm~ radiation dose rates from the steam generator (in the headers and
above the pipe still), measured after the completion of the second decontamination
cycle, were sharply reduced as compared to the initial level. The decontamination
coefficient of the various sections of the equipment averaged: 49 with respect ta
the cold header; 25 with respect to the hot header and 32 with respect to the pipe
still.
Similar results were obtained for the case of decontamination in two cycles of
the steam generators of another power unit. In the case of one cycle decontami-
nation, the decontamination coefficient was equal to 10.
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BIBLIOGRAPHY
1. "Dozy oblucheniqa personala Kol~skoy AES v per3od ekspluatatsii i remonta
oborudovaniya i puti ikh snizheniya" ["Personnel Radiation Doses at the
Kol~skaya AES During Equipment Repair and Operation and Ways of Reducing
Them"], A.P. Volkov, B.A. Trofimov, V.F. Kozl.ov, et al., in the book,
"Sovmestnyy sovetsko-angliyskiy simpozium po teme 'Ekspluatatsiya atomnykh
elektrostantsiy ["Joint Soviet and English Symposium on the Topic 'The
Operation of Nuclear Electric Power Stations Doklady SSSR [Reports of
the USSR], Moscow, VTI [All-Union Thermal Engineering Institute imeni F.E.
Dzerzhinskiy], 1977.
2. Sedov V.K., Baranov M.A., Vlasenko V.N., "Dozy oblucheniya personala AES v
protsesse ekspluatatsii, inspektsii i remonta. Puti 3kh snizheniya" ["The
Radiation Doses of AES Personnel During Operation, Inspection and Repair.
Ways of Reducing Them"), in the book, "Joint Sov~et and EnglfisR Symposium
on the Topic 'The Operation of Nuclear Electric Power Stations~", Doklady
SSSR, Moscow, VTI, 1977.
- 3. Balaban-Irmenin Yu.V., "Dezaktivatsiya oborudovan3ya AES. Trebovaniya k
proyektirovaniyu AES s tochki zreniya dezaktivatsii" ["The Decontamination
of AES Equipment. Requirements Placed on AES Design from the Viewpoint of
- Decontamination"], in the book, "Radiatsionnaya bezopasnost' i zashchita AES"
["Radiation Safety and AES Shielding"], Moscow, Atomizdat, 1977.
- 4. Couez H., Picone L.F., PROC. AMER. POWER CONF., 1971, Vol 33.
5. Ertel' K., Kherol'd K., Bernkhagen A., "Razrabotka skhemy i tekhnologicheskogo
reglamenta dezaktivatsii pervogo kontura na AES s reaktoram~ tipa'WER-~440"
["The Development of the Scheme and Production Process Regulations for the
Primary Loop Decontamination at AES's with type 'WER-440 Reactors"], Report
to the Conference of CEMA Member Nation Specialists on Topic 1-3.3, GDR,
Cottbus, 1979.
6. "Dezaktivatsiya oborudovaniya AES" ["Decontamination of AES Equipment"],
Yu.V. Balaban-Irmenin, I.M. Plotnikov, O.M. Ryazanov et a1, in the book,
"Joint Soviet and English Symposium on the Topic ~The Operat~on of Nuclear
Electric Power Stations "',,Doklady SSSR, Moscow, VTT, 1977.
~ 7. Golubev L.I., Dyukov V.F., Plotnikov I.M., "Dezaktivatsiya parogeneratorov
- Novovoronezhskoy AES" ["The Decontamination of the Steam Generators of tRe
Novovorone2h8kaya AES"], ATOMNAYA ENERGIYA, 1978, Vol 44, No 5.
~
COPYRIGHT: Energoizdat, "Elektricheskiye stantsii", 1981
8225
CSO: 8144/1064
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NON-NUCLEAR ENERGY
uDC 621.499;66i.961.62i;621.438.9
LNT?IiCY-S'I'ORiNG MA7'~RIALS AND Ti[LTR US~
Kiev LN1;itCUAKKUMULIftUYU:.~11CflIYL V1,'St1CH~STVA I IKH ISPOL'ZOVANIYE in Russian 1980
(si~r,ned to prc~:~ 2f3 J~l. E3U) pp 2, 238-239
[Anno~;ation arid tat~le of contents f'rom book "Energy��Storing Materials arid Their
Use", by I1'ya L'vovich Varshavskiy, Institute of Machine Building Problems,
UkSSR Acade~y of Sciences, Izdatel'stvo "Naukova dumka", 1000 copies, 240 pages]
[Text] The monograph discusses problems of using certain substances as secondary
enerf~r c~.rriers. Energy-storing materials are classified, and iheir energy
capacity is analyzed as well as methods of producing them. An evaluation is made
of the feasibility of using energy-storing materials to get hydrogen from water.
The book is intended for scientists and engineering-technical personnel special-
izing in the field of power engineering, ma.chine buildir.g and transportation.
Contents
7rt.ro~iu~:L~on 3
ChuF~t,er L. Lnerr?,y-~toriu~; Mat,eri~.ls b
l. Mz~t,eri:~lc thut rele~l: e c~ner~y with cnemir_a.l interaction 6
2. Material~ thr~t release ener~;y without chemical interaction 35
3. Lner~-storing materials from liquid slags ~9
4. Silicon as an energy-storing material 54
Chapter 2. Hydrides as Enex~ry-Storing Materials 60
1. Hydro~;en :,tora~?e units based on metal hydri des 60
2. ti,ydride-silanes 72
Chapter 3� Reactors for Producin~; Hydrogen from Water with the Use of
_ Lner~r-Storin~; Materials 79
1. 'i'~ieoreticra.l premises 79
2. Lxperimental reactor brzsed on energy-storing materials 100
Cha~~ter ~F. Ilydride 2'hermosor,ption Compressors and Their Use in Power
T;nKineeri.n~ 106
1. `1'tiermoc:Yierrdcul compression of hydrogen ' 110
2. Yower ~~lants witYi thermosorption compressors 113
3. Efficier~cy losses i Il s,ys t ems o f energy conversion and with thermo- 121
sorption compress~rs
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4. Thermosorption compressors in designs of fossil-fuel and nuclear elec-
tric power plants 123
5. Combined gas-turbine cycle 125
6. Production of secondary energy carriers in thermochemical cycles 127
7. Facilities with thermosorption compressors for liquefying hydrogen 133
8. Thermosorption compressors for separating hydrogen-isotope mixtures 142
Chapter 5. Use of Hydrogen in Heat Engines 1~+7
1. Studies on a one-cylinder facility 148
2. Studies on the Moskvich-412 engine 154
3� Use of hydrogen as a gasoline additive in internal combustion engines
with spark ignition 15$
4. Investigation of an internal combustion engine on hydrogen fuel in a diesel
~ cycle 162
5. Therm::dynamic analysis of operation of hydrogen-flzeled engine with
fuel obtained from water by using ener~-storing materials 169
6. U;e of ~ilicon as a~uel for transport engines 185
Ch~.pter 6. Converting Motor Vehicles to Operation on Hydrogen-Containing
Cuel with tl-~e U~e of ~nergy-Storing Materials 193
1. Conversion o~' ttie Moskvich-412 198
_ 2. Conversion of tYie VAZ-2101 to operation with hydride-stored hydrogen
additive 20~+
Chapter 7. Gas Turbine ~ngines and Steam-Gas Turbine Power Plants Using
Hydrogen Additives to the Main Fuel and Using Energy-Storing
Materials 209
l. Hydrogen additives to the main fuel in gas turbine engines 210
2. Ma,jor characteristics of gas turbine power plants with conversion to
hydrogen and to a mixture of water vapor and hydrogen 217
3. Thermod,ynamic calculation of working parameters of a steam-gas turbin~
power plant using energy-storing materials as fuel 225
References 233
COPYRIGIIT: Izdatel'stvo "Naukova dumka", 1980
bfi10
C~O: 1f3G1/ l02 ~
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CONSTRUCTION
unc 62~+.i3
- CONTINUOU~-ACTION ~XCAVATORS .
Moscow LK~~KIIVA`!'OfiY NL,PRLRYVNOGO DCYS'I'VIYA in Russian 1980 (signed to press
1~? ;;eF~ 80) 3~~-3~3
[Annotation and table of contents from book Continuous-Action Excavators. Second
Revised and Enlarged Edition", by 'Lalman Xeremeyevich Garbuzov, Viktor Mikhaylo-
vich Donskoy, Nikolay Vasil'yevich Karev (deceased) and Leonid Yermolayevich
Podborskiy, Izdatel'stvo "Vysshaya shkola"~ 35~00~ co~ie~~ 304 pages]
[Text] The book describes the power equipment and drives of continuous-action
excavators (chain and rotary trenchers, drain-ditching excavators, transverse
diggers, rotary and auger-rotary channel diggers, boom-rigged rotary excavators),
their construction, technical operation and organization of excavation work.
Contents
Introduction 3
Chapter I. General Information ~ 7
�l. CtiAracteristic: and classification of continuous-action excavators 7
�2. :~o:i].~; 12
ti:;. I'n,.rt i cu.lrir.~ o I' work tn~; {~roce:~:~e^ 18
1'Aft`P UNL;: I'UWLI~ LfZUlI'MLN'i' ANll DRIVLS
Chapter II. Drives from Internal Cumbustion Engines 28
�4. Ma,jor indices of engines installed on excavators 29
" �5. Clutches ~9
ChaF~ter I:it. Electric Urives r~nd rlectric Equipment 33
~ ~6. ~ources of electr~ic energy. Current supply 33
�7. Electric motor~ 35
�8. Protection and control equiprnent 39
�9. ~lectric motor control. Electric circuits
�10. Electric equipment of excavators with drive by internal combustion 46
en~ine
Chapter IV. Hydraulic Drives and Hydraulic Equipment 49
�11. Workinf; fluid ~9
~12. Hydraulic machines 51
�13� Hydraulic equipment 57
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511+. Tanks, filters and tubing 60
�15� Schematic diagrams of hydraulic drives 62
PART TWO: DESIGNS
Chapter V. Chain Trenchers 66
�16. Excavators based on caterpillar tractors 66
�17. Excavators based on roller tractors 81.
Chapter VI. Drain-Ditching Excavators for Drain Construction in Land
Reclamation Areas $7
518. General information 87
�19. Transmission 91
�20. Frame, pylon, conveyer and propulsion unit 94
521. Working equipment 95
�22. Controls 101
Cht~ptcr VTI. Drain-Ditchin~, Lxcavators for Drain Construction in Irrigation
Arens 110
�23. Ceneral information 110
424. Construction 112
�25. Controls 121
Chapter. VIII. Transverse DigQers 12~+
�26. Lr~nd reclamation exc~.vators 125
�27. Quarry e~:cavators 137
Chapter IX. Rotary Trenchers 11+5
�28. General informa.tion 145
�29. Tractor 150
�30. Transmission 151
�31. Working equipment 164
~32� Controls 171
Chapter X. Double-Rotary and Plow-Rotary Channel-Diggers 173
�33. Overall layout and kinematic diagrams '174
�34. Working equipment 187
�35� Transmission 189
- �36. Controls 196
Ctin~~ter X[. l1uNc~r-itotury 1,xczlvutors 199
� j'(. Over�;~1J. luyout ~lrid kinema.tic dit~~rrn.rr~s 199
~ 3f~. Workin~ equipment 213
�39� Transmission 216
�40. Contr~~ls 223
Chapter XII. Rotary Boom-Rigged Excavators 22~+
�41. Genera.l layout and kinematic di.agrams 226
�~t~. Workin~~ equi~~ment 232
�43, Controls. ~cFiematic dia~rram of electric equipment 237
YART TIIRL:i;: ORCANI'LA`PION ANll TECHNOLOGY OF EXCAVATION WORK
Ch~.pter XII:T . Fundament~~.l Information on Geodesy 242
�44. ~urvey of terrain 2~+2 .
�4j. Compila.ng a map of the terr~.in 249
~46. Profile of ttie terrain 250
~47. Calculatin~ areas 252
Chapter XIV. Technology and Orpanization of Production Work with Continuous-
Action Lxcavators 253
�48. Cener~.l inform~,tion 253
31
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�4y. Trench preparation ~5~
�50. Construction of channels 259
~51. Stripping and quarry work 263
�52. Drain construction in land reclamation 264
~53. Drain construction in irrigation 268
�54. Pipes used in constructing closed drainage systems 269
Chapter XV. Servicing of Continuous-Action Excavators 27~
�55� Ma~or requirements to be met by excavators before they can be put
into operation 270
�56. Basic principles of the system for servicing and repair of excavators 271
�57. Monthly servicing 272
�58. Planned servicing 278
�59. Lubrication 282
�60. Internal combustion engines 284
�61. ~lectric equipment 285
562. Hydra.ulic equipment 287
�63� Transportin~ excavators 290
�64. Storage of excavators 293
Chapter XVI. Organizing the Work of Excavator Operators 294
�65� Service personnel and their duties ~9~+
Q66. Settin~r up and testing equipr.?ent,e.nd delivering equipment for use 295
�67. Control of excavators in operation ~97
Chapter XVII. General Principles of Accident Prevention 299
COPYRIGHT: Izdatel'stvo "Vysshaya shkola", 1980, s izmeneniyami
66io
CSO: 1861/97
32
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NAVIGATION AND GUIDANCE SYSTEMS
UDC 355.58
I~'IHiNG t;1i011N1~'1'U-AIR M.IS3ILE:3
Moscow STREL'BA ZENITNYMI RAKETAMI in Russian 1980 (signed to press 10 Mar 80)
PP 292-295 ~
(Annotation and table of contents from book "Firing Ground-to-Air Missiles", by
Fedor Konstantinovich Neupokoyev, Voyenizdat, 12,500 copies, 296 pages]
[Text~ The theoretic~,l principles of firing ground-to-air guided missiles are
presented in the book, based on information from Soviet and non-Soviet open-
source literature.
The genera.l characteristics of ground-to-air missile systems are given; an exami-
nation is made of fields of application of various missile guidance techniques;
factors that determine errors of missile homing on a target axe analy~ed as well
. as parameters of the coordinate law of striking a target; methods are outlined
for calculating the in dices of firing effectiveness, and for estimating the space
and time capabilities of a ground-to-air missile complex.
TFic book i:s intended for :;F~ecialists in problems of combat utilization of ground-
~.O-r.~,lt" rti.i.:s:~ilt, com~lexe
- Con terite;
Introduction 3
1. General Characteristics of Ground-to-Air Missile Systems, and Essentials
of riring Groun d-to-Air Guided Missiles 6
1.1. Coo:rdiri~.tc ~y:~tem~. 1'~,r~.meters of motion of airborne target � -
Coor~i:inute ..y~tem:~ -
I.'arumetcr~ of moti.on of airborne tarpet 11
Uerivation of relr~tion~ between normal acceleration of a moving
F~o ini; , i t:~ ~~her i cut coordinates and their derivatives 18
1.2. :;,y:~ tem:~ f'or ~;ui d~,nce of ground-to-air missiles 22
~Tob:~ to be hr~ndled, and makeup of the guidance system -
Remote control command system 25
Mis:~ile tiomin~; systems 28
Combined ~;uid:.~.nce 33
1.3� Methods of producing guiding forces and torques 34
Maneuverability of the ground-to-air guided missile -
33
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Forces acting on the missile in flight 34
Torque~ actin~* on the missile in flight. Balance relation 39
/1v~~i.1+~b1e ~-forcce~ r~nd meneuverabi.lity of the guided ~;round-to-air
mi:;sile 42
1.4. Ground-to-air missile complexes 48
Makeup and general characteristics -
Ground-to-air missile complexes of non-Soviet armed forces 5~
2. Method:, of Controllin~ Ground-to-Air Guided Missiles 56
2.1. Determination of the method of guidance, and requirements to be .
satisfied -
Concept of inethod of guidance of remote-controlled missiles -
Concept of inetYiod of guidance of homing missiles 59
Pr~incipal requirements for methods of guidance 61
2.2. Methods of guidance of remote-controlled missiles 63
Dynamic errors of the method of guidance 66
Ttiree-point method
Method of linearization 72
Methods of complete and incomplete linearization of the tra,jectory 75
2.3� Methods of guidance of homing missiles 80
Evaluatiri~ methods of guidance of ground-to-air homing missiles -
Mettiod of pursuit 83
Method of 13uidance with constant angle of lead 89
Method of paral.lel approach 9~
MetYiod of' proportional approach 96
3. Concept of the Control Loop of a Ground-to-Air Guided Missile 1~5
3.1. Basic definitions
Requirements for the ground-to-air guided missile control loop -
Concept of the transfer function of the system 108
3.2. Transfer function of a missile with consideration of feedback ii7
3.3� Schematic of the control system of a guided missile
Command control loop of the missile
Homin~ loop of the ground-to-air guided missile 121
4. Nature t~.nd Sources of ~rror of Missile Homin~ on a Target 12~+
4.7.. clenera.l. c}iar~,cteristics of aiming errors '
4.2. Busic computational relations of the normal distribution law 126
4.3. llynamic error of missile homing on a taxget 131
Ilynamic error due to the limited capabilities of the missile with
- respect to g-forces 1~
Errors due to misc~lculations in compensation corrections introduced 133
into the control commands 137
fsrrors of trarisient processes
4.4. 1~'].uctur~t:iocicll arid instrumental errors of missile homing on a target 142
i~'l.uctu~.tional error of missile guidance 1~~
~ lnstrumentr~l ~;uidc~.nce error
1~.5. Inf'luence that twisting of the coordinate system has on the accuracy 1~8
oF ~;uidance of a~,round-to-air guided missile
4,G. I'robability of missile reaching a circle of given radius at the
target 152
~t.7. Concept of determination of errors in missile homing on a target 161
5. Action of the Warhead of a Ground-to-Air Guided Missile on the Target� 163
Coordinate Law of Striking the Target
5.1. Characteristic~ of fra~nentation warhead. Region of possible strike -
34
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Characteristics of fragmentation warhead 163
- Rej;ion of pos~ible strike 166
- 5.2. I~termination of the instant of detonation of the missile warhead
at the target 169
Region of radio fuse operation 170
Principles of operation of the radio fuse, and possible methods of
matching it with the missile warhead 172
5�3. Damaging effect of the warhead of a ground-to-air guided missile.
Vulnerability of an airborne target " 175
Characteristics of airbrone taxgets in brief -
Brisance 176
Shrapnel effect 177
- Cumulative action 180
Estimate of vulnerability of airborne targets 181
5�~+. Coordinate law of strike on a target -
Concept of coordin~.te law of a strike -
Approximate analytical representation of conditional law of strike
on a ~:ar~et 185
6. Methods of C~..lculut.in~r the Indices of ~ffectiveness of Missile Firing for
Given Charucteri:;tic:~ of the Law of Errors in Ground-to-Air Missile
Guidarice ~.nd a Coordinate Strike Law 188
G.1. Tcidices of effectivnes~ of firing at an airborne target -
6.2. t'robability of striking an isolated target 189
General relation for calculating the probability of striking a target -
Calculating the probability of striking a target with a single
missile 191
Probability of striking an isolated target with n missiles 199
6.3. Electronic counteraction, and antimissile maneuvering of airborne
targets 200
Electronic counteraction by ground-to-air missile complex -
Antimissile maneuvering 209
Estimate of probability of striking an isolated target under con-
ditions of electronic counteraction and maneuvering 210
6.4. Relirsbility of combat action of the ground-to-air missile complex 213
Some defi.iiitions -
Method of determining the coefficient of reliability of combat
action 214
~trike probability with con~iderr~tion of combat reliability of the
complex 217
6.5. ~vriluatin~,r effectiveness of firing ground-to-air missiles at a group
o f tr~rp;et:~ 218
I~'irinf; r~t ~~;rou~ of isolr~ted tar~,ets -
a.b. U~int; me~hod:~ of c~ucuinpr, theory to evaluate the indices of effec-
t~ivenes:~ 01' ttie ~;round-to-air missile complex 222
Conc~~~i: of queuin~ system. Computational relations -
On u~in~ the computational relations 225
7. Generalized Indices of Combat Capabilities of a Ground-to-Air Missile
Complex, and Factors that Determine These Indices 227
7.1. P~.ctors that determine the limits of the strike zone of the complex -
Basic definitions -
Factors that determine the ceiling and range of the strike zone 237
On the low-altitude limit of strike by the complex 2~+3
, Guaxanteed launch zone ~5~
- 35
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7.2. Capabilities of the ground-to-air missile complex in sequential firing
at targets 251
The firing cycle and its components -
Capabilities for fire transfer 253
7� 3� Limit of ,~ob performance and cover capabilities of the ground-to-air
missile complex 254
Limit of ~job performance -
Cover capabilities of the complex 255
8. Ground-to-Air Missile Firing System. Principles of Fire Control of
Divisions 259
~ 8.1. Essence of the concept and basic principles of the firing system -
- 8.2. Fire control of divisions, and requirements to be met 262
Essence of fire control
Requirements imposed on fire control 264
8.3. Distribution and designation of targets 267
Solution of the problem of fire distribution for a.irborne targets -
Assi�~ment of firing to divisions 269
8.4. Effectiveness of ground-to-air missile defense, and the concept of
methods of evaluation 270
APPENDICES:
l. Examples of transformed functions 275
2. Table of va.lues of the Laplace function 276
3. Tabl~ of values of P= 1- e-n 277
4. Probability of reaching a circle of predetermined radius with elliptical
scattering law and absence of systematic errors ~79
5. Table of values of the Hankel function of first order 281
6. Table of values of the function Je(K, T) 282
7. Values of norma.l distribution function 283
8. Values of probabilities Pf for missile corriplexes with small strike zone 287
9. Values of probabilities Pf for complexes with large strike zone 288
COPYRIGHT: Voyenizdat, 1980
6E~10
CSO: 1861/104
36
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~
~ 'Y
- FLUID MECHANICS
UDC 681.833.4.062.004.5
OYEItATiUN Uf~' MAIiI.NL }IYDRUACOUSTIC STATIONS
Leningrad EKSYLUATATSIYA SUDOVYKH GIDROAKUSTICHESKIKH STANTSIY in Russian 1980
(si~rned to press 19 Sep 80) pp 2, 189-191
[Annotation and table of contents from book "Operation of Marine Hydroacoustic
Stations", by Vladlen Anatol'yevich Pokrovskiy and Gennadfy Aleksandrovich Shche-
glov, Izdatel'stvo "Sudostroyeniye", 3500 copies, 192 pages]
[Text] The book gives ma,jor cliaracteristics of hydroacoustic stations. A de-
scription is given of standara measurement instrumentation used in technical
servicing of these stations. An analysis is made of factors that influence the
output functional characteristics of hydroacoustic stations, and a technique is
offered for quantitative evaluation of efficiency in using them.
The book is intended for marine radio navigators, and can be used by students in
institutions of higher and intermediate education that train hydroacoustics
specialists, and also by engineering and technical workers engaged in the design
and utilization of hydroacoustic facilities.
Contcrit:~
~ymbol~ 3
Preface 5
Introduction 7
Chapter 1. Output Characteristics of Marine Hydroacoustic Stations, and
Their Depen3ence on Various Factors 11
~ l.l. Factors that influence the output characteristics of hydroacoustic
- stations -
A. Acoustic field.~ of ob~ects of o?~servation -
B. Influence of.' the m~.rine environment 15
C. I.nterference to signal reception ~ 19
D. `I'echnic~,l condition of the 2~ydroacoustic station 21
1.2. Interrelation between output and technical characteristics of the
hy,~3roacoustic station 23
A. Ran~re of action 23
B. ~ccuracy of direction finding and resolution 29
,
37
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1.3� Influence that conditions of use have on the technical state of a
hydroacoustic station ~ 34
A. Degree of depletion of service life 36
B. Electrical loading conditions of elements and components of the
equipment 37
C. Climatic conditions 39
D. Radiation 43
1.4. Efficiency of utilization of hydroacoustic stations 4~+
Chapter 2. Principal Procedures in Technical Operation of Marine Hydro-
acoustic Stations 50
2.1. Fundamental concepts. Putting hydroacoustic equipment into use -
2.2. Checkin~ the technical condition of hydroacoustic equipment 58
A. Major quantitative characteristics of monitoring 59
- B. Basic procedures of monitoring, and its effectiveness 63
C. Par~;icular features of monitoring the condition of hydroacoustic
stations 66
2�3� Preventive procedures in the process of technical servicing of marine
hydroacou~i:ic stations -
2.4. Providing spare parts and accessories for the marine hydroacoustic
station 71
Chapter 3� Facilities for Monitoring the Parameters of Hydroacoustic
Stations 74
3�l. Electroacoustic instrument transducers -
3�~� Measurement oscillators 78
3.3. Acoustic pressure sensors 88
3�4. Displays and recorders 9~+ .
3.j. Equipment for analyzing phase and spectral characteristics 107
Chapter Procedure for poing Hydroacoustic Measurements During Operation
of the Hydroacoustic Station 117
4.1. Principal rules of doing hydroacoustic and electronic measurements -
4.2. Procedure for measuring parameters of the reception part of the hydro-
" acoustic station 126
A. Acoustic measurements 126
I3. Special electronic measurements 132
4.3. Procedure for measurin~; parameters of the transmitting part of the
hydroacoustic ~t~,tion 13~+
A. Acoustic measurements -
B. Special electronic measurements 135
Chapter 5� Procedu~e for Measuring the Level of Interference to Operation
of the Fiydroacoustic Station 136
5�1. Llectric interference to operation of the hydroacoustic station, and
measurement procedure -
5.2. Acou~tic interference to operation of the hydroacoustic station and
measurement procedure 141
Chapter 6. 'I'roubleshooting in Modules and Subassemblies of the Hydroacoustic
~tation 146
6.1. Factor:; �hat determi.-~e repairability of the station 146
6.2. Trouble:~hooting technique~ 152
6.3. Method: of elimin~,ting ma,jor malfunctions in the components and
subassemblies of marine hydroacoustic stations 161
Chapter 7. Lrgonomic Factors and Possibilities for Taking Them into Consider-
ation in the Process of Operating the Hydroacoustic Station 171
~ 38
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7.1. Role of the operator in the man-machine system 171
7.2. Some characteristics of the human operator with respect to reception
and processing of information from displays 1
73
7.3. Accounting for ergonomic factors in the process of utilization of
hydroacoustic stations 179
Conclusion 184
References 186 .
COPYRTGNT: Izdatel'stvo "Sudostroyeniye", 1980
6610
cso: 1861/l03
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MECHANICS OF SOLIDS
UDC 539�313
PLAT~;S AND SHELLS WTTH DISCONTINUOUS PARAMETERS
_ Leningrad PLASTINY I OBOLOCHKI S RAZRYVNYMI PARAMETRAMI in Russian 1980 (signed
to press 4 Apr 80) pp 2-5
[Annotation and table of contents from book "Plates and Shells With Discontinuous
Parameters", by noris Kuz'mich Mikhaylov, Ministry of Intermediate and Higher
Special ~d~cation, RSF5R, Izdatel'stvo Leningradskogo univeraiteta~ 1304 copies,
l~~i ~t~~r,e:: ]
(Text] The book presents methods of calculating shells and plates with ribs,
breaks, cuts and holes sub~jected to distributed and concentrated loads, based
- on ~eneralized (discontinuous) functions. Solutions are presented for problems
that come up often in computational practice.
The book is intended for engineers and scientists who deal with strength calcu-
lations of thin-walled three-dimensional structures and specialize in the thoery
of thin shells.
Contents ~
Introduction 6
Chapter 1. 1'rincipal Equations of Equilibrium and Deformations of Shells
with Discontinuous Parameters 9 '
l. Usin~ discontinuous functions to account for physical and geometric
lumped factors 9
2. Equations of ec~uil.ibrium anci deformations for shells with breaks 13
3. ~;~~uation~ of ec~uilibrium and deformt~,tions for ribbed shells 18
4. },'clua.tion~ of' ec~uilibrium t~nd deformations for shells with. cuts and cracks 20
j. Complex Lransforma.tion of differential ec~uations for shells with dis-
continuous para.meters 23
G. 1'rincipal re^olvin~, equations for cylindrical shells with discontinuous
parameter~ 35
8. Shells of revolution and near shells of revolution
Chapter 2. Action of Breaking Loads on Plates and Shells ~6
l. Solution of differential equations with pulse fur_ctions in the second
member ~7
2. Solution of differential equations with pulse functions in the case of
multiple roots of the characteristic equation 5~+
40
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3. Systems of equations with pulse functions in the second members 55
4. Effect that loads distributed along a line have on a plate 57
5. Effect that loads distributed along a line have on a shallow shell 61
6. Effect that loads distributed along a line have on a cylindrical shell 65
7. Spherical and conical ~hells under the action of a strip load 66
8. Effect of a lumped force on a plate and on a shell 70
9� Load distributed on the surface of a plate or shell along a line of
arbitrary shape 73
Chapter 3. Solution of Differential Equations of the Theory of Shells and
Plates with Discontinuous Coefficients Such as Delta Functions
and Their Derivatives 75
1. Solution of differential equations with variable coefficients that con-
_ tain delta functions 75
2. Another method of getting solutions of differential equations that contain
coefficients with delta functions of one vaxiable 81
3. Solution of differential equations with coefficients that contain
derivatives of delta functions 83
4. Solution of a system of equations with pulse coefficients that depend
on one variable g~
5. An equation that contains discontinuous coefficients with factors that
depend on two variables ~
6. Solution of differential equations with pulse coefficients that depend
on different variables g4
7. Proof of validity of formula (6.3) 99
8. Simplifications in the solution of equations with pulse coefficients.
Construction of matrices with zero components 102
9. Application of inethods of solving equations with pulse coefficients
to the solution of equations with variable coefficients in the form
of regular functions 112
Chapter 4. Shells with Breaks in the Midcile Surface 116
1. Shallow shells with breaksin one direction 116
2. Shallow shells made up oP strips of positive curvature 123
3. ~hallow ~hells mt~de up of strips of negative curvature 125
4. F'olded prismatic shells 127
5. f'olded pyramidal shells close to conical 133
6. Ca1ci.Llation of shelis made up of flat elements 136
Chapter 7. Calculation of Multiple-Wave Coverings 142
1. Calculation of single-span multiple-wave covers made up of shallow shells 1~+4
2. Calculation of sir.gle-span multiple-wave covers with hinged shells 156
3. A multiple-wave cover made up of shal.low shells resting on contour com-
ponents of lengthwise-variabl.e stiffYiess 158
Chapter 6. Pl~.te:~ rind Shells with Cuts 162
1. Ylate with a cut Eu1rr~.llc1 to one side of a rectangutar planform 162
2. E:xtimple o� cfllcu.lat;ion of plfLte with cut 169
3� Verification of' ttie: mettiod of' calculation f'or the special case of a
cylindrical t?inge alon~ the entire plate 174
4. Appl.ication of the pro~~osed method to calculation of a beam on an elastic
b as e 176
5. A bendable platc with several cuts 180
b. A~~late with rectangular hole 182
7. Shallow shell with cuts in one direction 18~+
8. Shallow stiell with rectangular hole 188
9� Cylindrical shell with cuts 190
COPYRIGHT: Izdatel'stvo Leningr~,dskogo universiteta, 1980
6610
cso: 1861/ioi 41
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~ UDC 53~+.232.001.11
DYNIIMIC-LNLRGY RELATIONS OI' OSCILLATORY SYSTEM~
Kiev llINAMIKU-ENLfiGLTICHESKIYI; SVYAZI KOLE~ATEL'NYKH SISTEM in Russian 1980
(sil;ned to press 14 Jul 80) pp 2, 186-187
[Annotr~.tion ~,nd table of contents from book "Dynamic-Energy Relations of Oscil-
latory Systems", by Aleks~.ndr Yevgen'yevich Bozhko and Nina Moiseyevna Golub,
Institute of Machine Building Problems, UkSSR Acadeiqy of Sciences, Izciatel'stvo
"Naukova dumka", 1000 copies, 188 pages]
[Text] This monograph gives the results of studies of the interrelation between
c~ynamic and energy processes that take place in oscillatory systems with free
and forced oscillations. Harmonic, polyharmonic an d unsteac~y forces are con-
sidered as forces of excitation. These studies are extended to a broad class of
oscillatory systems: Iinear and nonlinear, with one, two and n degrees of
freedom.
Examples are given relating to systems of reproducing vibrations and active
vibrution protection based on electroc~ynamic exciters.
'1'I~e t~ook i~ intended for ~cientists , en~ineers , graduate students ma.~oring in the
field of v.ibrution equipment design and vibration testing of machine~ and instru-
merit,:;, ~.rici ~,l~o for ~.dvanced etudents in engineering colleges. Figures 26,
rel'crence:~ 36�
Content~
Preface 3
Chapter 1. Free Oscillations of Linear Systems 5
1. Dissipative characteristics of oscillatory systems 5
2. Energy relations in a system with one degree of freedom 8
3. Systems with two degrees of freedom 13
4. Systems with n degrees of freedom ~7
Chapter 2. Forced Oscillations of Linear Systems 38
1. Motion of systems with one degree of freedom under the action of an
applied harmonic perturbation 38
2. F'olyharmonic excitation of systems with one degree of freedom 45
3. Systemc with two de~;rees of freedom under the action of a harmonic
constraining force . 50
42
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4. Polyharmonic excitation of systems with two degrees of freedom 57
5. Systems with n degrees of freedom under harmonic action 63
6. Systems with n degrees of freedom under polyharmonic action 71
7. Systems with unsteac~y action 73
Chapter 3. Free Oscillations of Nonlinear Systems 86
1. Particulars of nonlinear systems 86
2. Conservative nonlinear systems $9
3. Harmonic linearization of equations of motion of conservative systems 93
4. Systems with viscous friction 102
5. Systems with nonlinear velocity dependence of the force of friction 107
6. Self-oscillatory systems 111
Chapter 4. Forced Oscillations of Nonlinear Systems 114
1. Nonlinear conservative systems 111~
2. Ultraharmonic and subharmonic oscillations of systems 122
3� Discip~.tive systems with nonlinear force of elasticity 138
4. System:, with nonlinea.r f'riction 142
Chapter 5. Lner~~ Analysis of Uscillations of Electroc~ynamic Vibrators~ 148
1. Lner~ dissip~.tion by vibrators 148
2. Optimum dissipative characteristic~ tliat correspond to the maximum mean
power of vibrators 159
3� Maximum power of vibrators in reproducing polyharmonic vibrations 162
4. Energy relations in active vibration protection systems 168
5. Dynamic characteristics of active vibration protection systems 175
References 184
COPYRIGHT: Izdatel'stvo "Naukova dumka", 1980
6610
cso: i86i/ioo
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TESTING AND MATERIALS
uDC 629 . 7. 0 36 : 5 39 . 4
~;RU~ ION .~'i'RL'N(;'Pll UG' COMl'UNI~,NT~ OF FLIGHTCRAFT ENGINES AND POWER PLANTS
Moscow L,RU'LLONNAYA i'RUClINO:;T' D~TALEY DVIGATELEY I ENERGOUSTANOVOK LETATEL'NYHIi
APPAHATOV in Rus~ian 19~0 (signed to press 4 Oct 80) pp 2, 243-2~+5
[~lnnotation and table of contents from book "Erosion Strength of Components of
Fli~htcraft Lngines and Power Plants", by Roman Grigor'yevich Perel'man, Izdatel'stvo
"Mashinoetroyeniye", 1000 copies, 248 pages] ~ ~
[Text] The book outlines the theoretical and engineering aspects of erosion
- stren~th when fluid particles interact at high velocities with a solid. The
characteristics of erosion strength are given for some materials, as well as ~
methods and examples of digital computer calculation of blades in compressors of
gas turbine engines and nuclear turboelectric space vehicle power plants. Some
recommendations are made on designing items with required erosion strength.
The book is intended for aviation industry engineers.
Contents
Preface 3
SECTION I. STRUCTURAL STRENCTH OF ENGINE AND POWER PLANT COMPONENTS UNDER
THE DYNAMIC ACTION OF WORKING FLUIDS 7
Chapter 1. General Problems of Erosion Strength 7
1.1. Erosion strength as one of the classes of structural strength 7
1.2. Classification of types of erosion destruction of materials and parts 22
Chapter 2. Basic Meteorological Parameters that Cause Erosion 23
SECTION II. PFiTNCIPLES OF THE TH~ORY OF EROSION STRENGTH WHEN FLUID
PARTICLES STRIKE A SOLID 31
Chapter 3� Determination of Loads on the Surface of a Part Interacting with
~ Yarticles and with a Gas-Liquid Stream
3.1. Impact with a hydraulically Smooth Surface 31
Influence of fluid properties 37
Determination of Rayleigh wave parameters
3.2. Interaction of the flow that forms as a particle runs off a surface 47
Model of surface action of a gas-liquid stream 47
Interaction of radial flow with polycrystalline materials 51
44
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3.3. Impact of a liquid particle against depressions in a plate 58
Pressure on the bottom of a gas-filled indentation 5$
Pressure on the bottom of a liquid-filled indentation 60
Pressure at the tip of a crack situated on the bottom of a liquid-filled
depression C2
Chapter 4. Characteristics of a Two-Phase Flow and of Particles that Interact
with Components of Flightcraft, Engines and Space Vehicle Power
- Pla.~zt s 61~
4.1. Influence of the ambient medium on the characteristics of a liquid
particle before impact (1~
Subsonic flow 65
Supersonic flow 79
4.2.. Characteristics of particles that erode the blades of gas turbine
zngine compressors 83
4.3. Parameters of liquid flow in the turbines of nuclear turboelectric
space vehicle power plants 85
l'~,ttern of' flow movement $5
Determination of' the parameters of particles acting on the working
b l~lde s $7
Ctia~ter 5. 1)estruction oi' a Solid by a Discrete F'low of Liquid 90
>.1. Limitecl role of cavitation phenomena in the case of high-velocity action
of' prir�ticles 90
- 5.2. l~'undam~ntal criteria of erosion strength 93
5.3. Periods of erosion destruction and the way erosion is affected by the
relief of the surface being worn away 102
5.4. Particulars of destruction of brittle materials 115
SECTION III. EXPERIMENTAL STUDIES OF COLLISION OF LIQUID PARTICLES WITH A
. SOLID, AND OF THE MOTION UF LIQUID PARTICLES IN THE AXIAL GAP
OF TURBOMACHINERY 117~
Chapter 6. Collision of an Isolated Particle with a Plane 117
6.1. Damage produced by single particle 117
6.2. Determination of characteristics of loading by a liquid particle 124
~ Using a st~.tionr~ry piezosensor 125
Usin~ hi~r~-speed and ultrahigh-speed motion picture photography 127
The method of' rotatin~; pi.ezosensors 133
G.3. Investi~,ation of stresses in the surface of a component�with droplet
impact lor~din~, 137
`1'he method of dynamic photoelasticity 137
'Ptie mettiod c~f holuf;rfipYiic interferometry 142
Cli:lpter 7. Mu.ttiple Cotlis ion of ~'articles with a Plane 144
'T.1. M~.thods ~.nci facil:it.ies for liquid impact erosion tests 144
7.2. :3ome known ct?ar~.cteri:~tics of' erosion strength of materials 148
"(�3. I)ro~>let imp~.ct (,jet imp~,ct) facility 154
llevice:s for� producin~ stxeams of droplets 156
S~ecimens th~,t ure used 159
7.4. Test results 160
Inf'].uence of ambient medium on dimensions of the maximum contact spot 160
Comparr~t-ive ero~ion properties of droplets and ~ets 162
Kinet:ics of erosion wea.r of inetals and alloys 166
Charr3,cteristics of materi~,ls necessary for calculating erosion strength 171
7.5. Erosion strength of composition materials 179
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7.6. Modelir?~, of erosion stability 181
In the region of fatigue fracture 181
In the region of material flow 182
In the region of brittle fracture 186
Chapter 8. Investigation of Erosion Stren gth of Alloys in Alkali Metals and
Vapor 187
8.1. Methods of evaluating the corrosion-erosion strength of alloys, and
substantiation of these methods 187
8.2. Testing equipment 191
8.3. Results of tests of alloys 19~
CHAPTER IV. PROBLEMS OF PLANNING AND CALCULATION FOR EROSION STRENGTH OF
COMPONENTS IN GAS TURBINE ENGINES AND NUCLEAR TURBOELECTRIC
SPACE VEHICLE POWER PLANTS 206
Chapter 9. Method of Machine Calculation of Erosion Wear of the Working Vanes
_ in Air-3ireathing Jet Engine Compressors and Nuclear Turboelectric
- I'ower Plant Turbines 206
9.1. Ano.lytical model of ~i,he change in shape of working vanes with Wear 206
9.2. Difference scheme of solution 212
9.8. On ca.lculating the parameters of streams of droplets 21~+
_ Chapter 10. Working Conditions and ~xamples of Calculation of Erosion of
Components 216
10.1. Calculation of erosion of working vanes in the first stages of gas
turbine engine compressors 216
Calculation of erosion of the gas turbine engine vanes in a supersonic
transport plane 221
10.2. Calculation of erosion of the vanes of wet-steam turbines in nuclear
turboelectric space vehicle power plants 224
References 233
- COPYRIGHT: Izdatel'stvo "Mashinostroyeniye", 1980
6610
C~o: 1861/9y
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UDC [621.311.25:621.039.002.5]:546.3:65.012.7.004
IMPROVING THE EFFICIENCY OF SELECTIVE TESTING OF THE METAL OF NUCLEAR ELECTRIC
POWER STATIODI EQUIPMENT
Moscow ELEKTRICHESKIYE STANTSII in Russian No 4, Apr 81 pp 8-10 ~
_ [Article by V.N. Gulyayev, candidate of the engineering sciences, "Energiya"
Scientific Production Association of the USSR Ministry of EnergyJ
[Text] High reliability of tiie metal and the welded ~oints of equipment should
be assured~in the operation of nuclear electric power stations.
Monitoring during the operational process must be set up so that primarily those
parts or their xones which are the most dangerous from the viewpoint of the
possibility of the occurrence of damage are inspected with selective monitoring
with minimal expenditures and so as not to violate existing instructions, where
there is a max3mua? of confic~ence in the reliability of the results of selective
= checking.
The efficiency of selective monitoring can be increased, when the factors
considered in the following are taken into account.
There is a considerable scatter in properties in parts~ especially those made
of thermal strain hardened steels. This scatter in properties is customary in
world practice and is explained both by the fluctuations in the actual chemical
composition of the steel (or alloy) within the range of a brand of steel and the
application of standard heat treatment schedules at the plants, these schedules
are specified as a whole for a standard steel camposition for a given specific
product.
For example, the processing of the certificate data on 205 pipes of 47 melts,
intended for the boiler plants of thermal electric power stations, showed that
the scatter was as follows: 25 kgf/mm2 for the yield stress; 20 kgf/mm2 for the
ultimate strength; 12.5 percent for the relative elongation; 30 percent for the
contraction ratio and 14.7 kgf � m/cm2 for the impact toughness.
Operational experience with conventional thennal electric power stations shows
that the equipment camponents undergo brittle rupture primarily in the case of
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Z kgf�m/cm2
, . . , ~ ,r.c�n/cN
' ~ . r. ~ I 36pN~ - I
' J.
; a ~ j ! ; ~ ; ~B ' az - -
~ I ~ I I o I ' o a~ o' o
, ~ ~ ~ ' i - - - 70 ~ oCO, . _ 4--- - a ~ oo ~
o ~ o ~ ' . 7B o
~ ~ o..o ~ h~ Q I ye �g Qoo d~
;S ~ ~ - ~
I 60 64/L 69 7: %6 1~ Krc MNZ 2 2's` p
!r I I o I ~ 6� \u~ 6~ Ag~~21[QL O
36 60 6f 6B 77 76 Kic/Nr.' o
0
~a) a~ j~S~~~2 0 0
16
Figure 1. Graphs of the relative elongation (a), the ~z o.
O d~ ,
contracti.on ratio (b) and the impact toughness e
(c) as a function of the ultimate strength at a6 60 6e ~z �/~r
20 �C for one of the types of alloy steel. (c~ e~ kgf~ffin
inadequate metal ductility. Since increasing the strength and hardness is, as
a rule, accompanied by a reduction in plasticity, ascertaining especially high
strength and hardness indicators during the input quality control in individual
products or regions of them can be evidence of inadequate ductility and a
tendency to brittle fracture, i.e., the most dangerous damage.
Various steels, depending on the alloy, have various ductilities for the same
level of strength [1]. For products which have already been fabricated, it is
necessary to take into account the ductility and the impact toughness of the
metal when monitoring and sampling dangerous regions (from the viewpoint of pos-
sible damage).
The relative elongation, the relative contraction ratio and the impact tough- '
ness are shown in Figure 1 for one of the brands of alloy steel.~ For the case
where the upper ultimate strength is limited to a value of 68 kgf/tmn2, the
indicators for the plastic properties and the impact toughness increase.
The conclusion can be drawn that in the case of selective monitoring,
primarily those products or regions of them should be checked, the metal of which
has the highest strength and hardness indicators.
To reducc the probability of damage to metal, the following requir ~nent is
stipulated in the rules of the State Committee of the Council of Ministers for
the Supervision of Industrial Safety and Mining Inspection [2]: the value of the
ratio of the yield stress to the ultimate strength (a~g/vg) at room tempe~rature
should not exceed 0.6 for carbon steels, 0.7 for alloy steels and 0.8 for alloy
reinforcement steels.
In actual products, the value of Qg/QB for a metal can vary in a rather wide
ran~e. Thus, pipes, the scatter in the properties of the metal of which was
given earlier, were distributed as follows with respect to the value of ~S~QB~ ~
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Percentage
- aS~~B of
Pipes of the Total
Numb er
< 0. 7 33 15.1
> 0.7--< 0.75 29 14.1
> 0.75--< 0.8 100 48.8
> 0.8--< 0.85 39 19.0
> 0.85--< 0.875 4 2.0
The role of the og/o~ criterion is rather clear wlien Figure 2 is considered, from
which it can be seen that there is a linear relationship between the value of
ag~Qg:and the number of. cycles before destruction in tests for short-term fatigue
at a specified deformation amplitude [3]. A similar linear function is likewise
characteristic of tests for thermal fatigue. The greater the value of ag/vB, the
fewer cycles the metal sustains for destruction.
An analysis of a ninnber of faults in the primary medal and welded joints at
conventional TES's [3, 4] has shown that damage was primarily observed where
the requirement concerning the value of the ratio vg/Qg was not met. Since AES's
are used to carry the base load and operate with a emaller number of starts and
shutdowns of the equipment than conventional generator sets with capacities of up
to 200 MW and nonmodular TES installations, higher ultimate values of the ratio
os/6B can be permitted for the metal of AES equipment.
1000 . . ..n . - - - -
Figure 2. The graph of the relationship between the number
"0 - of cycles before destruction in the tests of
su~~- 15 GNM and 22 k steels for short-time fatigue
for the case of a deformation amplitude of
vou - a a 1 percent and the ratio of the yield point to
Z00 ~ ~ �
a,ss qsn o,ss a,~v o,~s u,eu the ultimate strength.
Regardless ot tlie setting of these ultimate values, the effectiveness of
selective monitoring of the metal and welded joints of AES equipment is improved
- iF those elements or regions of them where the values of ~g/~g are maximum are
~iven priority in the testing.
- The val.ucs of the ultimate strengths Qg can be taken frmn the certificates or
d~tcrm(ned based on har.dncss measurements during input quality control during
- tt~e rqutPment inst~llation period. The yield stress og is likewise in the
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certificates for the primary metal or can be determined using nondestructive
techniques [S, 6J.
When determining the regions of equipment whibh require increased attention
during testing, it is likewise necessary to take into account the possible
change in the metal properties c~ue to transformations wfiich take place in it at
the working teperatures during operation.
At conventional TES's, pipe bends are the most subject to damage, besides welded
joints [7], where the operability of pipe bends depends not only on the properties
of the metal and the thermal treatment following bending, but also on the ovality,
since with an 3_ncrease in the ovality, the actual stresses in the bends increased
[8]. This cir.cinnstance predetermines the expediency of ineasureznents during the
acceptance t~sting for the ovality of bends and the priority monitoring during
operation at those bends which have the maximum ovality.
Piping made of austenitic stainless steel ~s found widescale applications at
AES's. The qua].ity of the weld joints of such pipes and their functional capa-
bility during operation depend on the ferrite phase content in the metal of the
pipes and in the deposited weld metal. Because of this, it is necessary to check
the ferrite content in each pipe during input quality control.
It should be noted in conclusion that the large volume of data on metal properties
obtained during the input quality control makes it difficult to use them in an
operationally timely manner when testing during the operational process. Because
of this, the problem arises of designing a monitor system around computers. The
latter, based on the metal properties from the certificate and documents of the
input quality control which are stored in their memory, as well as the values of
the existing stresses, should feed out reco~endations for specific equipment or
regions in it which are to be given priority in monitoring during operation.
Conclusions
It is e~cpedient to do the following for the purpose of improving the efficier.cy
of selective monitoring of inetal and weld joints during operation:
--Determine the equipment components or regions of them, the metal of which is
the most inclined to brittle f.ailure, during input checking based on the analysis
of certificate data as well as the results of hardness and yield stress measure-
ments;
- --Use nondestructive techniques to determine the ultimate strength and yield
stresses of individual regions of weld joints and bends, as well as for the
primary metal in some cases;
--Give priority to the checking during the operational process of those components
or regions of them by nondestructive methods, where reduced values of the
ductility and impact toughness, as well as high values of the strength properties
and the QS/~B ratios are combined with the maximum acting stresses;
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--'Pake into account the ferrite content in the metal of pipes for the weld joints
of piping made of austenitic steel.
BIBLIOGRAPHY
1. Bungardt K., Kiessler H., Kunze E., STAHI, UND ETSEN jSTEEL AND IRON], 1954,
Vc1 74, No. 2.
2. "Pravila ustroystva i bezopasnoy ekspluatatsii parovykh i vodogreynykh kotlov"
"Set-Up and Safe Operational Regulations for Steam and Hot Water Boilers",
Moscow, Nedra Publishers, 1968.
3. Gulyayev V.N., "Kontr~l' kachestva metalla--na elektrostantsiyakh'~ ['~Moni.toring
Metal Quality at Electric Power 5tat~ons"], BE7.OPASNOST~ TRUDA V PROMYSI~iLENNOSTI
~ [LABOR SAFETY IN INDUSTRY], 1973, No 2.
4. Gulyayev V.N., "K voprosu kontrolya metalla shpilek armatury" ["On the Question
of Monitoring the Metal of the Stud Bolts of a Fitting"], ENERGETTK jPOWER
ENGINEER], 1973, No. 1.
5. Markovets M.P., Karashchuk A.F., "Sravneniye razlichnykh metodov opredeleniya
predela tekuchesti po tverdosti" ["A Comparison of Various Methods of Deter-
mining the Hardness Yield Point"], ZAVODSKAYA LABORATORIYA [THE PLANT LABORA-
TORYJ, 1961, Vol 27, No. S.
6. Drozd M.S., "Opredeleniye mekhanicheskikh svoystv metalla bez razrusheniya"
["The Nondestructive Determination of tne Mechanical Properties of Meta1"],
Moscow, Metallurgiya Publishers, 1965.
7. Aksel'rod M.A., Telezhkin V.M., "0 povrezhdeniyakh gibov trubnykh sistem kotlov
i paroprovodov" j"On Damage to Bends in the Pipe S�ystems of Boilers and Steam
Lines"], in the book, "Metall v sovremennykh energoustanovkakh" ["Metal in
Contemporary Power Installations"], Moscow, Energiya Publishers, 1972.
8. Ulrzch E., MITT.~VGB [not further defined], 1960, No. 64..
COPYRIGHT: Energoizdat, "Elektricheskiye stantsii", 1981
8225
CSO: 8144/1064 END
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