JPRS ID: 10240 WORLDWIDE REPORT NUCLEAR DEVELOPMENT AND PROLIFERATION

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• Document Creation Date: November 1, 2016
• Sequence Number: 9
• Content Type: REPORTS

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JPRS L/ 10240
7 January 1982 ~ ~
_ orldwide Re ort
- W p
- PIUCLEAR DEVELC~QI`~1ENT AND PROLIFERATION
- CFOUO 1/82)
Fg~$ ~OREIGN BROADCAST INFORMATION SERVICE
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JPRS L/10240
7 ~anuary 1982
~
WORLDWIDE REPORT ~
; NUCLEAR DEVELOPMENT AND PROLIFERATION
(FOUO 1/82) .
_ CONTENTS
EAST EUROPE
CZE~HOSLOVAELLA
PM-3652 Nuclear Power Station Diagnostic System Outlined
- (Kaxel Prokop, et a1.; ENERGETIKA, No g, 1981) ~ 1
Direct Conversion of Nuclear Energy to E].ectricity Discussed
(Jiri Racek; ENF~GETIKA, No 9, 1981~ 16
SUB-SAH~RAN AFRICA
1VIGER
Briefs
President on F`rench Uranium Negotiations 30
SFNEGAL
Agreement Establishing I~Tucler~r Materials Compar~y ~ Appro~ed
(MA.RCHES TROPICAtTX ET MEDTTERRANEIIVS, 13 Nov 81) 31
WEST EUROPE
FRANCE
~ Briefs
Nuclear Research Discussions 33
- ITALY
New Organizatio:~ of National Nucleax Energy Committee
(ATOMO E INDUSTRIA, 1 Sep 81) 3~+
_ - a - [III - WW - 141 FOUO]
F(lA !1F'FT!'i A T T TCF l1NT V
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~ F(1R (1PF1('l:11. l'tii~: ON1.1'
~ C'LE~HOSLOVAKIA
,
PM-3652 NUCLEAR POWER STATION DIAGNUSTIC SYSTEM OTJTLINID
Prague ENERG~TIKA in Czech No 9, 1981 pp 386-392 .
I
[Article by Eng Karel Prokop and Eng Milan Novak, EGI, Dukcvany Nuclear Power
Station, and Eng Svatobor Stech, Dukovany Nucle3r Power Station Concern: "The
PM-3652 Nuclear Power Stat~ion Diagnostic System"] ~ .
[Text] Currently, industrial equipment is bzcoming increasingly complex and ex-
pensive. This also increas.es the need to assure its optimal operating condition,
reliability and technical safety. These requiremenrs c~n be met only if we have
informatioY;.on the processes.taking place in the equipment and on the devices and
structural ~nembers which assure proper operation. For this purpose it is essential
to monitor the condition of the equipment and processes taking place in it and to
provide f.or signaling of unsafe (i.e., extraordinary or emergency) conditions.
Modern methods for evaluating the state of processes and equipment include analysis
' not only of short-term average values of ineas~ired parameters, but also of cha=iges
in these parameters, for the changes brought about by a process conta~n import~nt
informatiou about it. The cl~aracteristics of a dynamic process are its amplitude
a.ld frequency spectrum. In information engineering, the technique of ~valuating
statistical fluctuations of signals has been called "noise analysis." This method
is particularly suitable for comprehensive monitoring of processes. .
In continuous measurement of the characteristics of a process, we primarily monitor
the occurrence and development of deviations from measurement values corresponding
to normal states of the equipment. In this way, we can identify the cause of an
abnormal state and detect processes of equipment damage in their i.r,iti~l stages.
It is advantageous to use the period when the equipment is being broken in (e.g.,
the startup of a nuclear power station), when it is highly probable that the equip-
ment and components are functioning correctly, to measure the characteristics of
the normal state.
Analysis of the noise componerits.of various signals, including pressure, temperature,
neutroa f lux, vibration and the live, has led to noteworthy results in diagnosis of
- processes occurring in such pressure vessels as nuclear reactors and reactors in the
chemical and metallurgical industries. An advantage of thes~ methods is that they
do .r,.ot require direct contact of the sensor with the working medium.
1 '
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To solve the problems noted abuve fur nuclear reactors, the ~'`1-3652 nui~e aualysi:;
system has been developed. '~his system allows diagnosis of damage to nuclear reac-
tors and has been tested under operating conditions for several years. It include~
monitoring of vibrati~on in the reactor, its interior components and thP control
equipment drives; in addition, the system records the pres5ure values of the Goolant
in the reactor (pressure pulses) and the neutron f~ux inside and outside the r~actor.
The system also has instruments to locate loose components in the pressure vessel and
primary circuit. All of these parameters are measured si.multaneously by the PM-3652
~ system. Analysis of the noise components of the measured quantities (noise coraponents
of signals) makes it possilhle not only to obtain short-term average va1~~2a but also
to determine the temporal (long-teran) trends of 4uch parameters. Tnis maices it
possible to monitor possible undesirable trends in paz~ameters, which has special
importance for diagaosis of reactor states.
_ Purpose of the System
Measured Quantities, Measurement Locations and Sensors
For noise diagnosis in an operating nuclear reactor, the following quantities are
monitored:
a. The neutron f lux density in the reactor core is measured by beta emiss~on de-
tectors;
b. the neutron flux density outside the reactor is measured by ionization chambers;
c. the coolant pressure at the reactor inlet and outlet and at selected locations
in the primary circuit is measured by piezoplectric sensors;
d. vibration of the pressure vessel, the control assemblies and the main circulating
pumps is measured by piezoelectric sensors.
Choice of ineasurement locations is based on calculations using mathematical models.
The sensors are located where computations indicate that vibration problems are
likely to be indicated most clearly.
Information Content of Neutron-Flux Density SignalG
Of the measured quantities listed above, neutron noise gives the most extensive
information. Almost all important processes in a nuclear reactor are reflected to
some degree in the time trend of neutron-flux density. Thus, evaluation of these
~ processes becomes possible. through evaluation of neutron-flux density trends, using
computations based on matl:~matical models derived from nuclear reactor theory.
- The noise composition of the neutron-flux density signals is infliienced by the
following effects:
a. changes in reactivity produced by vibration of components inside the reactor or
- by coolant in::omogeneities;
b. changes in the neutron-flux density produced by coolant inhomogeneit.i_es or
changes in the thickness of the water-filled space between the reactor barrel and
,
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the pressure vessel resulting from vibration of the =eactor rdrrel; in this case
we treat the core as a neutron source and the neutron detector is outside the
reactor; .
c. changes in the neutron-flux denisty outside the pressure vessel resulting from
movement of the core as a whole or of its individual components; this involves
~ changes in the position of the neutron source relat~.ve to the neutron detector
located outside the reactcr;
d. local disturbanc~s in the neutron-flux density inside and�outside the core
resulting from effects operative in a particular location, e.g., inhomogeneity of
the coolant, steam bubbles, local vibration.
Information Content of Pressure Signals ~
On the basis of previous experience, pressure pulse measurements can be used to infer
J the following effects (sources of pres~ure pulses):
a. prFSSUre p ulses produced by the main circulating pumps; the frequency of the
pulses is governed by the rotary frequency of the main circulating pump vanes and
by their higher harmonics; ~
b. pressure pulses res~.ilting from char.ges in the hydraulic resistance of the inner
fixtures of the reactor; these changes result from vibration of the components
inside the reactor produced by coolant f low;
c. pressure pulses resulting from the geometry ef the reactor cooling circuit;
d. press~ire pulses resulting fram turbulence in the coolant.
Information Content of Vibration Sensor Signals
The signals from the vibration sensors include mechanical movements of the components
or r.onnecting syst~ms to which the sensors (accelerometers) are attached. However,
the sensors can also detect vibrations originating far away from them.
- In order to be able to sense the most impor~ant vibration problems, we locate the
vibration sensors:
a. on ~lie prESSUre ves~el flange where the reactor barrel is suspended, making it
possible tn sense hcrizontal and vertical movements of the barrel;
h. at suitable locations on the pressure vessel wall, e.g., in the zon~ of the
intake and outlet connectors, in order to sense their vibrations;
c. at selected locations in the primary circuit where maxi.m~m vibration may be
= exnected, i.e., the main circulating pumps, the steam generators, and pumps in the
primary circuit auxiliary systems.
There are various sources of'mechanical vibration, such as the main circulating
piunps, movem~nt of the main shutoff valves, the control-assemb].y drives, and coolant
flow.
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The sensor placement described above~gives us the following main capabilities:
1. monitoring the functioning of the main circulating pumps, the main shutoff valves
and the controT-assembly drives; .
2. detecting the existence of loose parts in the primary coolant by evaluriting
tapping (impact) against the walls and structural components; .
3. sensing and monitoring the mechanica~ ~vibrations o� structural components (e.g.,
seizing of bearings and the like).
Measuring Apparatus ~
_ The measuring apparatus, a block diagram of which is given in Fig 1, consists of
the following components:
a. a signal sensor (detector);
b. a preamplifier locar,ed near the sensor;
c. the ~onnecting cable bezween the sensor and preamplifier;
d. the smplifier;
- e. a programming unit;
f. evaluating equipment.
- Fig 1. Block diagram of PM-3652 noise
analysis system
. a b c d
0e(oF:ry arod~.rtlow~' r ; s .y~eenoco.n~i
xuKUh aKUtaro J-ypp~wovoai ~o,vy.~
Key :
~ s-m~, ~ao~ ~
. a. Detectors r ~
e~arued~i ~ ~,Y~Mn~ 1
b. Preamplifier close to deL,ctor >oTO~. ~i f~.c g
c. Amplifier with programming unit ~�i~ ,
d. Evaluating equipment t~`,"~. C:s'~~? s~~~~�_ ih�~",.`~
~ 'i ~e~
- e. Ionization chamber
PmTd ~a.,v,~,. ~ r. .r n
. f. Nuc,lear signal preamplifier box Q k
w;raci ~ru! ~~s Y~ ' n~ednao- ' a~n~ ~
g. Ma:tn nuclear signal amplifier box ri;~ n: o.~~ ~
h. Vibration meter s _~~q k~:� ~
~rcne~:,,.; � ~ ~ �~~.i: � i T ngniA v;0
i. Six-channel oscilloscope ~
j. Digital.voltmeter ~
k. Box containing evalL~ating equipment Obr. 1. Blokovb schbma syseEmu, tumovE anol~szy - PM 3652
1. Real-time analyzer
m. ~Stereo amplifier and speakers in housing
n. Vi'bration meter and coordinate plotter ~
o. Tape recorder (recording oh magnetic tape)
- p. Pressure pulse sensor
q. Preamplifier
r. Mechanical signal amplifier box ~
s. Accelerometer
t. Emission Detector
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The main technical problem in noise analysis is separation of relatively low~level
noise (0.01-2 percent) Erom the average values of the main signal. In the subse-
quent stage, the problem is amplification and transmission of the signal so that the
desired signal stands out clearly against the backgrourrd interference. These re-
quirements are met by means of preamplifiers whose design allows a signal to be
transmitted over a relatively large distance without losing its quality.
~ensors.
Available l.nformation on the number and location of sensors varies. A surv2y of
these data is given ir Tables 1, 2 and 3, which show the nianbers of individual types
of sensors according to references 1, 2 and 4,. Fig.2 has been developed according,
- to the latest information [3, 4] supplemented with data from reference 5; it shows
the measurement locations in the primary circuit. The five sensors located in the
volume compensator [5; are, according to reference 4, a special arrangement which
was used only during the startup period. Currently, the volume compensator at the
Bruno Leuschner nuclear power 5tation has no sensors (units 3 and 4), but it is
planned to equip this important part of the primary circuit with some sensors in
units 5 and�6. However, no specific data are available. The location of sensors
' in the reactor can be seen from Fig 3.
, Table 1. Sensors and their locations (data from technical information on PM-3652
system [1]). .
Sensor Number Location
~ Emission detectors 30 Core
KS-30/1 vibration sensors 1 Base of pressure vessel
4 Plane of bottom of pressure.vessel,
spaced at 9~�
4 Plane below level of pressure vessel ~
connectcions, spaced at 90�
4 Plane of pr.essure vessel flange, spaced
at 90�
= 3 Main circulating pumps (one sen~or
per pump)
2 Control-assembly drives
UDE-150e pressure pulse sensor 1 Pressure vessel: coolant intake
1 Pressure vessel: caolant outlet
- 2 Between main shutoff val.ve and main
circulating pump
y
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Table 2. Survey of sensors (data~ according to reference 2)
Sensors ~
30 Sclf-powererl neutron-flux detecrors in groups of five in six channels �
inside the reactor vessel
10 Ioniz3tion chambers for measuring neutron flwt, in groups of two with ~
different sensitivities in five channels in the water 3acket surrounding
the reactor vessel. The high-sensitivity detector is used during startup
- and the low-sensitivity detector during power production
1 Piezoelectric vibration sensor on base of pressure vessel ~
- 4 Piezoelectric vibration sensors on surface of vessel below the core
4 Piezoelectric vibration sensors on surface of vessel above the Core
4 Piezoelectric vibration sensors on surface of vessel between pipe connections
4 Piezoelectric vibration sensors on flange.of vessel
2 Piazoelectric vibration sensors on control-assembly tubes
, 3 Piezoelectric vibration sensors on outlets of the three cir~ulating pumgs
2 Piezoelectric pressure fluctuation sensors on outlet piping of two c.irculat-
ing pumps .
1 Piezoelectric pressure fluctuation sensor on vessel near one intake connection
_ 1 Pi~~zoelectric.pressure fluctuation sensor on vessel near one outlet c~nnection
.Table 3. Survey of sensors used in units 3 and 4 of Bruno Leuschr~~r nuclear power
station (data a~ccording to reference 4)
~ Type of sensor Number of senso~s in: '
One unit~ Z~ao units '
~ Se~f-powered (emission) detectors 60 ~ 120 .
- Ianization chambers . , 6 12
PressLre pulse sensors . ' 8 ~6 ~
Vibration sensors 52 104
Total number cif sens~rs 126 252
Special attention must be devoted to transmission of signals from the sensors to
- the preamplifiers and to the design of the preamplif~ers themselves~ It must be
assured that during signal transmission over a relatively long path there will be
no undesirable attenuation or distortion resulting fzom interference in the signal
path. '
Emission Detectors
Neutron-flux density in the reactor is~measured by beta-emission detectors. Rhodium
detectors 200 mm long are located at 5 vertical levels, in guide tubes.
Detection of local changes in the neutron-flux densi*_y requires measurement at a
relatively large number of points in the reactcr core.
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~oR oFFic~:~i. ~~st~~ oN~.~~
Fig 2. Measurement locations in primary circuit (for information purposes)
Key:
. ;
- a. Ionization chamber ~
b. Pressure pulse measurement
c. Vibration sensor ~
.
. " ~ :
~
. ~
~ � ;
. - ~
'
_
L---~ � roe~robri kono~n
D rnb'an Nekavrti~/ulnci
� C � minwf ribrci
~ Obr. 2. Mflic! mista v prim6relm okruhu (informotivn! udoje)
--t- -
I i
i ~
I
I
I
. I - - -
~ ~
Fig 3. Location of sensors on reactor I~! ~
~
~
~ , A
- a
Key : ~ - , - ~ iontzac~nt komor~x
, I ~
a. Ionization chamber ~ ~ ~i ~
b. Emission detectors r I � ' r em~sni de{ek:o~y b
c. Pressure pulse sensors ; ~
_ d. Vibration sensors ~ i `sn{rnace ffokovycl~pu!zaci ~
~ ; ! ~snimac~e ahv~ni (vibraci) d
-
~ i I
_ i ~
~ .i
~ I I
I
J
Obr. 3. Umistl~nf snlmo?'u na reoktoru
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The instantaneuus detector curr~iit vtilue is used iur ~inise :inaYysis: tlie trac�f~r
factor for the noise signal is: ~
K~ = 3 x 10 21 [amp-sec-cm2/particle]
The signal is fed from the detector to a preamplifier lacated close to it, and from
there to the main amplifier.
Ionization Chamber
"i'he neutron-flux density in the space around the reactor is measures by ionization
- chambers located in the bio2ogical shiald. The ionization chambers are mo~~ble
vertically along the core zone. ~ ,
= The transfer factors are:
K~ = 6 x 10 15 [amp-sec-cm2/particle] (power rarge);
, K~ = 10 12 [amp-sec-cm2/particle] (startup). '
- The signals from the ionization chambers are fed to preamplifiers located close to
them and from there to the main amplifiers.~
Vibration Sensors
Piezoelectric sensors capable of ineasurement in a range from 2 Hz to 10 kHz are
used as vibration sensors. The transfer f~ctor is:
Bq = 20 [pC/g] ~
The signals from tne vibration sensors are fed to greamplifiers located.close to
them.
Pressure-Pulse Sensors � ~
- Pressure gulses at the reactor intake and outlet and at various locations in the
primary circuit are measured by pressure-pulse sensors. ~
The transmission factor is:
; Bq = 350 [pC/MPa] .
With an average working pressure in the vicinity of 12 MPa, the sensors can register
pressure pulses down to 4 p= 2 kPa�
- P~eamplifiers
The preamplifiers increase the power level of the measured signal, thus allowing it
to be transmitted over some di~tance; otherwise there would be undesirable attenu-
ation and distortion. The preamplifiers must be located as close as possible to
the sensors or detectors, i.e., within 5 to 20 meters.
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~
Preamplifiers for Nuclear Signals
The preamplifiers (current amplifiers) for the measurement signals of emission
detectnrs and ionization chambers are located, along with the power supplies foi
the emisston detector channels, in the preamplifier box, clase to the reactor. The
signal inpst and output leads are joined to the box by connectors ~o that the box
can be disconnected when working with the reactor.
Vibration and Pressure-Pulse Signal Preamplifiers
These are symmetrical discharge amplifiers whose transfer factors a~e so chosen
' that the output signal f or vibration (acceleration) is l0a mV/m/sec = 1 V/g; for
the pressure-pulse sensor output signal it is 2 V/MPa.
Main Amplifiers
The main amplifier unit consists of two boxes containing not only the amplifiers
themselves, but modular c~mponents for power supgly, signal labeling, signal
division (splitting the signal into short-term average values and noise components,
amplification of noise components to a common level) and channel selection. All
madular components and f~nctional groups, inserted units, chassis and boxes are
standardized. This design allows effective use of spare parts and rapid repair.
Main Nuclear Signal Amplifier Box
~ This box contains modular components of the main and dividing amplifiers for
; processing the signals from the emission detector.s, with two limiting value signals
' (positive and r.egative limiting values) and modular si~gnal labeling components.
The group of channels carrying emission-detector signals from the p~eamplifiers
' which is chosen for evaluation may be sel.ected manually. The signals.from the
ionization chambers are amplif ied and monitored for values in excess of the limits.
Compensating and integrating amplifiers allow further processing of the ionization
chamber signals. An adjustable integrating amplifier i~ used to integrate the
signals from several ionization chambers when the reac,tor is at low power and to
determine average values of location-dependent effects.
The compeusating amplifier allows precise measurement of deviations in the average
values of the ionization chamber signals; these are used to determine the effective-
ness of the control assemblies as a~runction of their position.
Main Mechanical Signal Amplifier Box
The main amplifier box contains amplifiers equipped with signals indicating that
limiting values have been exceeded; these amplifiers are used to process signals
from vibration and presssre-pulse sensors, which can be tapped with earphanes or
loudspeakers. In addition, the box contains modular signal labeling and power sup~-
ply components. ~
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Evaluation Equipment
, The PM-3652.13 evaluation equipment consists of the following devices:
a. a six-~=hannel oscilloscope;
b. a digital voltmeter;
c. a universal device for vibration measurement consisting of an oscilloscope, an
indicator, a narrow-band analyzer, a control unit for processing the stgnal and a
graph plotter; ~ ,
d. a measurement point selector;
e. an output p~.nel for a computer;
f. an output for a magnetic tape recorder;
g. a signal labeling unit.
Technical Data
Dimensions of box (meters):
preamplifier box 0.6 x 2.1 x 0.6;
main amplifier box 0.8 x 2:0 x 0.6; .
- evaluation equipment box 0.8 x 2.0 x 0.6.
Sensors, Preamplifiers and Amplifiers
A survey of the transfer factors and output signals of preamplifiers and amplifiers
for various types of sensors is given in Table 4.
The OPD 280 U Six-channel Oscilloscope
This is a slow-speed oscilloscope: ~
sensitivity 0.5 V/cm �
input impedance 5 megohms .
input frequency 0-10 kHz ~
screen diagonal 280 mm.
The Q-1206.010 DC Digital Voltmeter ~
~ Measurement range 1 microvolt-1 kV (six ranges)
Maximum sensitivity 1 digit per microvolt
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Table 4.
7ob. ~
1~ 2~ ~nimat 3 I ~F Fledzesilo~�nt ~ Zesilo~uC ~
:~If'~rnri ~�clii�inn T~~ ~ suintuL�c F'i�enosucc fal:tor
T fierne.:,.~`
Ruzsali treke.ncf I p~noso~~j~ ' rtFtupni signLl c$etupni aigaAl6
~ 2aktor 5j 6 i P faktor 5
zr;~clilriii i0 I"i? 30 1 i~q � 20 pC'g 5(~ m~';pC 1 C!g r~ 316 31f g
I ~ Hz 1G bHz = l0U 1(~U ~'~q
I I" r s 31,8 31,f ~;g
~ 10 10 ~ IB
i = 3,16 3,18 ~ ~g
( r ~ 1 1 ~'!B
, tlak 11 QDE 15uc I Bp = 350 D~'~IFn 3,7 mC~gC : ~II~iPu ~ a 316 632 C!DIPa
~ 0.1 Hz . 10 kFiz ~ s 100 200 ~�~IPa
n ,31,u � G,3 ~'IDLPu
P ~ lU 3 ~ '1IPn
� C ~ 3,16 U,63 ~"~IPa
I ~ 1 0,: r1~LPa
1
`iu~t~~tn fuku I b~�tu-cmieid Aerm' ~Teom' ~'ecm'
13 ~ ~~o-=� ~o c~ua 3.10-~~ s.10-� ~~ttce 15
ti~ucr�i,u 12 acse�kc~r , m"�~ r�,~,cf;ec ~aecieel5
~iu-cor~�~ I . � recm' ~'ecm'
14 3,3 ~'f�:1 10''~ ,~tice lU0 10''t ~eticc
~ i ~gem' 1f Cecm'
I 1'r/uS 3.10-" ~stlce 3.30' ~,isiice
- hustotn toku ionizaL'n( ~ecm' ~ Vecm` recm'
" nentrnnu 1 komora 1~ s~ = 6.1U-" 10 ~'I�A 6.15' 15 lUU 18,9.10~' ~Asttee 15
(out-core) S'~FC 57 AI ~314e CAatfoe
I 1~'/�:~ 6.10-~ ceom' V ~ 31,6 8.]0-~~ Cecm'
Leetice c - 13.18 , tJytICC
~ ~ osem' ~ = 1
I 0,1 ~i�:~ 6.1U-' t~tice
~ ~'ec�'
0,01 rl�A 8.10'" ~tice
.I i ~
! hustota toku iovizaL~nf I .~ecm' ~ecm '
neutronu 1 komora 17 Fm = 10-" 10 Vj�:~ 10'' ~ti~ 0~ 816 8.16.10-~ ~ Lice
~ {out-core) ~ I'i~Ii 56 ~sticc 1 v~]00 15
Vecm' V a 31,6 Cscm'
1(} 1~'/�A l0~' ~stioe s 1~~ 10_~ Gaeticc
~ oecm' ~ ~ i~16
I 0,1 ~ if+~ 1~- ~~tioe
vecm'
I O.U1 ~'I�A I 1J~' BAetice ~ �
Key:
~ 1. Measured quantity I0. Acceleration
2. Type of sensor 11. Pressure
3. Sensor, transfer factor, 12. Neutron-flux density (in-core)
frequency range 13. Beta-emiss~on detector
4. Preamplif ier 14. Amp-sec-cm /~particle
5. Transfer factor 15. Volt-sec-cm /particle
. 6. Output signal 16. Neutron-flux density (out-core)
- 7. Amplifier 17. Ionization chamber
_ 8. Transfer factor
9. Output signal
Vibration-Measuring Instrument
Section powered from electrical
~ System (11031) 22C~J/110V
External source--battery 12 V ~
11
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11 163 Narrow-Band Analyze~c .
Frequency range .0.2 Hz-20 kHz
Relative bandwidth 3%, 10%, 30% ~ ~
11 018 Hig~-Pass Filter
Limiting frequency 16-500 Hz (switchable by half octaves)
11 025 Indicator Unit
Indicator ~ Effective, positive and negative peak
(maximum) value
~ Frequency range 1 Hz-15 kHz
11 028 Oscilloscope
Frequency Range 2 Hz-15 kHz
- Time base speed 300-0.03 msec/cm (tangential)
X: horizontal sensitivity 20 mm/volt
. Y: vertical sensitivity 8.5 or 22-75 mm/volt
Real-Time Analyzer (External Devi^e) ~
Frequency range 20 Hz-20 kHz
Measurement capability Instantaneous, peak (maximum) value '
Filter and broadband ~
. channels 30 channels by thi=ds of an octave. ~
5 broadband channels
Input resistance 100 kohm
- Location of Devices
The spatial arrangement and .location of the sensors and preamplifiers is described
in the section on measuring apparatus and in Tables 1, 2 and 3. For servicing
reasons, it is recommended.that ~he amplifier boxes and evaluating equipment boxes
be located close to the computer used for signal analysis.
Survey of Instruments Included in Noise-Analysis System
Name Ty~e ,
Sensors
_ Vibration sensor KS 30/1~
Pressure pulse sensor QDE-150e
Emission detector (ED)
Ionization chamber (IK)
Connector cable 5700/20
12
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FOR OFF[ClAL USE OrILY
PM 3652.10 Nuclear Signal Preamplifier Box
Emission-detector signal amplifier 4386-110
' Ior.ization chamber signal preamplifier 438fi-120
SR~-13 stabilizer ~ 4882-13
- Transformer T~I388
Section powered by electrical system 3301-24
P1ug-in unit with blower ~
Power system connection panel
Lamp and fuse panel
Connector panel .
4386-335 Mechanical Signal Preampiifier ~ ~
Preamplifier.connecting block
- PM-3652.11 Nuclear Signal Main Amplifier Box
Main emission-detector signal amplifier 4386-210
Compensating amplifier 4386-22i
Compensating amplifier 4386-2:?2
Integrating amplifier 4386-21`; .
- Separating amplifier: ID .
and signaling labeling 4386-211 ~
Separating amplifier: ~ ~
' IK and IK channels 4386-225
Main amplifier of IK signal 4386-330
Relay unit 4386-48401
- Signal labeling unit switch 4386-215
Signal labeling unit matrix C 4386-485
Modular power supply � 3204/15
Modular power supply 3307/15
Power system connection panel '
Power supply control unit ~ '
Program panel (manual program selector)
Output signal panel
Ionization chambe?- power supply 4486-50
- PM 3652.12 Mechanical Signal Amplifier Box
Main mechanical signal amplifier 4386-330
_ Signal labeling switch 4386-215B
Signal labeling unit matrix C . 4386-485L
Amplifi.er for earphone 4832-03A
Modular power supply 4882-33
Modular power supply 4837-20
Modular power supply 4387-31
- Switch panel (monitoring)
Output signal panel ~
Aectifier and filter unit
Transformer ~
Power supply cable panel
_ Programming unit 4386-340
13
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FOR OF'FICIAL USk: ONLY
PA 3652.13 Evaluating Instrumentation Box
, Six-channel oscilloscope OPD 280/U
Digital voltmeter G 1206.010
Vibration meter
Box 110 12 (BG 401) .
Power s}~stem section 11031 (SM 61)
Oscilloscope ~ 11028 (SM 50)
Indicator unit 11025 (SM 40)
- Narrow-band analyzer 11163 (SM 32) ' ~
Control unit PM 3310 (SM 71)
High-pass filter 11018 (SM 23) .
Signal labeling unit
- Measuring location selector
Panel for output to computer
Panel for output to recording device
- Panel for connection to power system
- Modular powe;. supply (5V/6A)
Modular power supply 3307/15
Evaluating Instruments
Real-time analyzer 01012 .
_ Stereo amplifier HSV 921 ~
Speaker box B9301 ~ ~
Note: The technical design of the system allows an increase in the number of
- measuring locations. .
System Capabilities
The noise-measurement analysis system has the following features and capabilities:
1. It has multiple uses in nuclear engineering and the chemical and meta.llurgical
industries.
2. It allows monitoring of the operating condition of equipment which is not
equipped with measuring and regulating systems.
3.~ It gives timely signals of chaages in an operating process or the occurrence of
damage to machinery and equipment. It can be used to evaluate the probable cause
of damage, and thus makes it possible to prevent breakdowns and emergency conditions
in process equipment.
4. It provides data for planning of inspections and repairs, and can be used to
plan the necessary scope of work during planned equipment stoppages. This raises
equipment maintenance to a qualitatively higher level.
5. Equipment repairs can be limited and the interchange system can be used for
smaller radioactive components. ~
~4
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6. It allows the detection and location of loose parts. This prevents major
damage to equipment, excess shutdowns of the power s~ation anci the resulting loss
_ in power produced.
7. It processes and evaluates signals from vibration, pressure, temperature and
_ tieutran-flux density sensors, ~nd can conduct frequency and time analysis of the
measured values.
BIBLIOGRAPIiY
- 1. "Rauchmesssystem PM 3652, Technische information [Technical Information on
PM 3652 Noise Measurement System]."
" 2. Jonak, F. "Moderne metody registrace a hodnoceni mechanickych vibraci primarnych
okruhu JE s lehkovodnymi reaktory a zakladny pristro,;ove vybaveni [Modern Methods
- of Recording and Evaluating Mechanical Vibrations of the Primary Circuits of
- Nuclear Power Sta.tions Using Light-Water R~actors, and the Basic Instrumentation
. Used]." UJV-4347, Rez, September 1978.
3. Trip report on business trip to East Germany on 5-11 October 1980.
4. Information presented by East German specialists at a seminar on the diagnostic
system for nuclear power stations using VVER-440 reactors, held on 15 January
1981 at UJV [Nuclear Research Institute], Rez. .
S. Giera, D.; Schumann, P.; Lot, K; and Eberbach, A. "Opyt razrabotki, proyektiro-
vaniya i primeneniya vo vremya puskonaladochnykh rabot i ekspluatatsii AES
sistemy ustanovok dlya diagnostiki, rabatayushchikh na osnove analiza shumov
= [Development, Design and Use During Nuclear Power Station Startup, Adjustment
and Operation of a Noise-Analysis System of Diagnostic Devices]," C-80-10/GDR.
- COPYRIGHT: SNTL, 1981
8480
CSO: 5100/3006
15 '
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~clK c~~~lc'i:~t. t~~r' t~~l.l'
~ ~ CZECflOSLOVAKIA
DIRECT CONVERSIQN OF NUCLEAR ENERGY TO ELECTRICITY DISCUSSID
Prague ENERGETIKA in Czech No 9, 1981 pp 393-399 ~
[Article by Eng Jiri Racek, Electrical Engineering Faculty, WT [Technical Institute],
Brno: "Methods of Direct Conversion of Nuclear Energy to Electrical Energy"]
[TextJ Types of Direct Conversion of Energy to Electricity
The main sources of energy for the production of eZectricity can be divided into
the following groups:
--the energy of solar radiation;
--chemical enexgy;
--hydraulic energy; .
--geothermal energy; ~
--nuclear energy. ~
The energy.of solar photons h~ats and illuminates the earth and is.converted into
the kinetic energy of marfne currents, wind in the atmosphere and waves on water
surfaces, into the gravitational potential energy of clouds and streams bf water,
and into the energy accumulated in plants. We may consider chemical energy (parti-
- cularly fossil fuels) as solar energy accumulated in the depths of the earth in the
course of its geological development. In the broad sense, then, we may 9:nclude all
of these energy sources in the category of solar energy.
The natural flow of geothermal energy is fed by two sources, namely heat accumulated
- in the depths of the earth and heat newly created within the earth, primarily by
. natural radioactive processes. In practice, it is frequently difficult to distin- '
guish between L~.se of the natural flow of g~othermal energa and use of the stored heat.
The energy balance is shown in more detail in Fig 1. '
~6
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F6R OFFICIAL USN: UNLY
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