JPRS ID: 9108 USSR REPORT ENGINEERING AND EQUIPMENT

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• Sequence Number: 45
• Content Type: REPORTS

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JPRS L/9108 -
~ 2~ May 1980
- USSR Re ort
p
ENGiNEERING AND EQUIPMENT
~ CFOUO 5/80~
~
F
~BIS FOREIGN BROADCAST INFORMATION SERVICE
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JPRS L/9108
27 May 1980
USSR REPORT
ENGINEERING AND EQUIPMENT
(FOUO 5/80)
CONTENTS
MARINE AND SHIPBUILDING .
Elementary Theory of Submarines
[Annotation, introduction and table of contents from book
by Yuriy Ivanovich Bol'shakov, Voyenizdat, 23,000 copies,
136 pages] 1
NUCLEAR ENERGY
- Operating Modes of Water-Cooled, Water-Moderated Nuclear Power
- Reaci~ors
[Foreword and table of contents from the book "Ekspluatat-
sionnyye Rezhimy Vodo-Vodyanykh Energeticheskikh
Yadernykh Reaktorov" by Fedor Yakovlevich Ovchinnikov,
_ Lev Ivanovich Golubev, Vyacheslav Dmitriyevich Dobrynin,
Viktor Ivanovicin Klochkov; Vladimir Vladimirovich Semenov
and Valentin Mikhaylovich Tsybenko, Izdatel'stvo Atomizdat,
Moscow, 2nd edition, signed to press 3 July 1979, 4,100 copies,
288 pages] 6
Outlook for Develop~ng a Nucleax S:ingle-I,oop Helium Turbine System
With a High-Temperature Reactor of One M311~on k~]e Power 10
NON-NUCLEAR ENERGY
Steam-Generating Units Opexating on Sea Water
[Foreword and table of contents from the book "Parogeneratornyye
- Ustanovki na Morskoy Vode" by Leonid Illarionovich Sen' and
iuriy Vladimirovich Yakubovskiy, Izdatel'stvo Sudostroyeniye,
Leningrad, 1979, signed to press 13 June 1979, 3,700 copies,
232 pagesJ 13
System for the Overall t#utomation af Compressor Statinns 16
- a~ [III - USSR - 21F S&T FOUO]
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CONTENTS(Cont~nued)
MECHANICS OF SOLIDS
Vibration and the Strength and Stability of Complex Mechanical
Syetems
[Annotation and table of contents from the collection of works
"Kolebaniya, Prochnost' i Ustoychivost' Slozhnykh Mekhani-
cheskikh Sistem," edited by L. Ye. Borodyanskiy and T.V.
Katsovenko, Dnepropetrovsk Department, Institute of Mcehanics,
Ukrainian SSR Academy of Sciences, Izdatel'stvo Naukova
Dumka, Kiev, 1979, signed to piess 4 April 1979, 1,550 copies,
163 pageaJ 17
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MARZNE AND SHIPBUILDING
ELEMENTA,RY THEORY OF SUBMARINES
Moscow ELEMENTARNAYA TEORTYA PODVODNOY LODRT (Elementary Theory of Subma-
rines) in Russian 1977 signed to press 26 Oct 77 p 2-4, 133-134
[Annotation, introduction and table of contents from book by Yuriy Ivano-
vich Bol'shalcov, Voyenizdat, 23,000 copies, 136 gages]
[TextJ Thi~ book sets forth, in a popular fashion, the relation of
buoyancy to the size and shape of a submar~ne, the change in buoyancy during '
submersion, surfacing and floating under water, the change in stability
- during submersion and surfacing, during shifting of cargo, settling on
the bottom, docking and running aground, the unsinkatsility of aubmarinea
- above water and under water, and calculation of ballast trim. The book
is intended for the self~instruction of submarine personnel. It can be
used as a textbook for Nava1 inatructional detachments.
Introduction
Submarines, in order to carry out their assigned tasks, must t~ave completely
well-defined qu~lities. The so-called seaworthy features of submarines
- occupy an important place among them: buoyancy, stability, unsinkability,
propulaive performance, controllability, and rolling. Subma~cine theory
is the acience of its seagoing qualities. Knowledge of submarine theory
enables submarine experts to predict the behavior of a submarine in various
floating cnnditions, to make maximutn use of its seago~ng qual~ties, and to
~ take the necessary measures to prevent defects.
Each crew meattber of a submar3ne must etf~ciently and profeasionally perform
hie duties, work skillfully while water ~s entering the vessel~s hull,
strictly observe weight requirements, be aware of the harmful effect of
excessive cargo, of a change in ballast trim of the submarine during its
submersion and surfacing, and also of a decrease in atability during aub- '
marine docking or bottoming. _
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_ Submarine specialists, who are directly responsible for the effective
utilization of the fast, maneuvering features of a vessel, for maintaining
ita proper acoustical characteristics, for ballast trim and asaurance of
atability and uneinkability of the submarine, must know perfectly the
theory of submarines. The rapid and aophisticated aolution of an entire
set of problems under yar}ting._aa~igating _cQad#Li,ons degends o.n skillful
guidance based on knowledge of submarine theory and experience of the
submarine specialists. Without a deep understanding on the part of sub- _
marine specialists of such seagoing qualities as navigability and the prin�-
ciples for operation of. propelters, efficient utilization of the submarine -
power plan~ is impossible, and for precise fulfillment of different submarine
maneuvers one must be well-versed in aspects of its controllability.
Development of the theory of submarines is closely related to development
of ahip construction. Academician A. N. Krylov has played an important
role in the history of Soviet ship construction and development of ship
theory. The famous scientist and shipbuilder_I._G.:B.ubnov did much �mr the
practical impr~vement of the seagoing features of submarines. The service
of Soviet scientists, designers and Naval officers in the cr.eation and
_ development of modern submarine ~.heory is very great. Such scientists
and ship engineers as V. G. Vlasov, P. G. Goinkis, D. L. Garmashov, K. F.
Ignat'yev, S. V. Kozlov, B. M. Malinin, N. Ya. Mal'tsev, P. F. Papkovich,
E. E. Papmel', D. P. Skohov, G. G. Sallus, K. K. Fedyayevskiy, Yu. A.
Shimanskiy, A. N. Shcheglov and others have made important contributions
to the development of submarine theory. ~ -
In improving the counbat and seagoing �eatures of modern submarines, Sovi~*.
scientists and designera promote all-out growth of the power of our sub-
marine fleet.
Our submarine crewa, in carrying out theix duty to their Morherland,
are mastering modern, complex combat techniques, are improvin~, their skills
and are increasing their profeasionalism. This book is intended to help
them in this matter.
In this book an attempt is made for the first time to set forth in an
elementary fashion submarine theory, taking into consideratiou the require-
ments of the Unifled System of Deaign Docwnentation and the International
Syatem of Units (ST) and other standards documents. Therefore, it was
considered wise to use new designations and forms of tables. In some
cases the author thought it possible to preserve the symbols and designa--
tions traditionally used in submarine theory, although they do not conform
to standard documents.
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The author ia firmly of the opinion that graphice and clear expooition
are more importa~t for Nava1 pereonnel than mathematical correctneae.
Therefore~ in a num~er of caese~ ~trictneae of demonetrations gave way to
graphic deecription and clnaraees of preeentation of the problem. The
author expressea his deep indabtednese to Rear-Adm. R. D. Filonovich, Rear-
- Adm S. S. Ivanov, Engr-Capts 1 st rank N. N. Yefim'yev and V. K. Tokmakov
for their careful examination of the nanuscript and their ever valuable
criticiam and advice, and he also aincerely thanks the honored worker of
the RSFSR Engr-Capts 1 st rank Ye. P. Shikanov for his direct help in set- -
ting forth submarine theory from the position of modern requirements.
Table of Contents "
rage
Introduction 3
Chapter 1. General Information on Submarines .5
1.1. General information on the structure of submarines -
1.2. General assumptions of the theory 14
Chapter 2. Buoyancy of a Submarine 20
2.1. The concept of buoyancy -
2.2. Displacetnent 24
2.3. Buoyancy reserve 25 _
2.4. Submersion and surfacing 27
Chapter 3. Change in Residual Buoyancy of a Submarine During
Navigation Under Watex 31
3.1. Residual buoyancy , -
3.2 Change of residual buoyancy due to change in water -
densi:~ 32
_ 3.3 Change of resi.:iual buoyancy of a submarine due to hull
compression 37
3.4 Change of residual buoyan.cy d~se to effect of temperature
of the hull 39
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Ghapter 4. Calculation of Ballast Trim of a Submarine 41
4.1. Loading -
~ 4.2. General assumptions of receiving, consumption and
replacement of cargo 43
4.3 The concept of weighixlg 44
4.4 Methods of calculating ballast trim 45
4.5 Esamples of ballast trim calculation 50 -
Chapter 5. Stability of a Submarine 55
5.1. General assumptions - _
5.2. Lateral metacenter and J.ateral metacentric radius of a
submarine in above-water pos3tion 56
5.3 Metacentric formula of initial lateral stability 59
5.4 Later~l stability of shape and weight 60
e c nt c hei ht b
5.5 Determination of lateral m ka e ri g y
experimental means 62
5.6 Initial longitudinal stability in above-water position 64
5.7. Stability during large heeling angles 67
5.8. Concept of ~?S~namic stability 69 ,
~
5.9. Stability dur~ng triuuning 72 ;
, i
5.10. Stabil3ty in underwater posit~.on 73
Chapter 6. Change in Stability of a Submarine Under Varying .
Conditions 75 _
6.1 Change of stability due to vertical shifting of a cargo - -
6.2 ChangE of stability during receiving or consumption of a
. cargo
4 -
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6.3. Effect of excessive cargo on stability 83
6.4. Effc~t of non-Kingston tanka of the main ballaet on
above-water stability 87 _
6.5. Change of stability during docking and bottoming 88
Chapter 7. Change of Stability of a Submarine Duri:~g Submersion
and Surfacing 91
7.1. Change of stability during submersion and surfacing
without considering the effect of fluid, excess cargo -
7.2. Change of stability during submersion and surfacing
with consideration of the effect of excess cargo 95
Chapter 8. Unsinkability of a Submarine 99
8.1. Above-water unsinkability -
8.2. Underwater unsinkability 108
Chapter 9. Submarine Navigability 113
9.1. Resistance o~ air and water dux~.ng movement of a
submarine in above-water position -
9.2. Resistance of watex during movement of a subma~ine "
in underwater position 116
Chapter 10. Controllability of a Submarine 118
10.1. Controllability in horizontal plane
. 10.2. ControlXability in vertical plane 120
Chapter 11. Rolling of a Submarine 127
- Literature 132
COPYRIGHT: Voyenizdat, 1977
[46-9424J
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NUCLEAR ENERGY
UDC 621.039.56
OPERATING MODES OF WATER-COOLED, WATER-MODERATED NUCLEAR POWER REACTORS
Moscow EKSPLUATATSIONNYYE REZHTMY VODO-VODYANYKH ENERGETICHES-KIKH YADERNYKH
REAKTOROV in Rusaian 1979 pp 3, 287-288
[Foreword and table of contents from the book "Ekspluatatsionnyye Rezhimy
Vodo-Vodyanykh Energeticheskikh Yadernykh Reaktorov" by Fedor Yakovlevich
Ovchinnikov, Lev Ivanovich Golubev, Vyacheslav Dmitriyevich Dobrynin,
Viktor Ivanovich K2ochkov, Vlad~mix Vlad~m3.xovich Semenov and Valentin
Mikhaylovich Tsybenko, Zzdatel'stvo Atc~m~l.zdat, Moscow, 2d edition, signed ~
to presa 3 July 1979, 4,1Q0 copies, 288 pagea]
[Text] FOREWORD
The program for the development of nuclear power engineering in the USSR
provides for the conatruction of a large number of AES's in which the thermal
energy source is a water-cooled, water-moderated power reactor (WER).
- In connection with this,the correlation of information obtained during the
operation of WER's have been partially touched upon in the book "~kspluata-
' tsiya Reaktornykh Ustanovok Novovoronezhskoy AES" ("Operation of Reactor
Units at the Novovoronezhakaya AES"), which was written by F. Ya. Ovchinnikov
and others and publiahed by Atomizdat in 1972.
In this book the basic attention is focused on a discussion of the operat-
ing modes of WER's. ~
In 3.t we explain the principles of the neutron-physics, thermohydraulic
and physicochemical processes taking place in a WER and also systematize
- and correlate Soviet and foreign data on the operating modes of reactors _
of this type. The authors base their discussion of inethods for the theore-
tical prediction of the basic neutron-physics and thermohydraulic character-
istics of WER's on the pertinent developments made at the Institute of
Atomic Energy imen3 T.V. Kurchatov under the leader~hip of Doctor of
Technical Sciences V. A. Sidorenko, Candidate of Technical Sc~.ences G. L.
Lunin, Candidate of Technical Sciences A. N. Novikov, V.A~ Voznesenskiy
~ and others. The examples used in the explanat~.on of the operat~ng modes
are the Soviet WER-440 and WER-1000 reactors from Unit 5 at the
Novovoronezhskaya AES. _
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.
The sections that are basically concerned with the WER-1000 have been
reworked and added to for this second edition. The other of the explanation -
of these materials hae been changed and a number of refinementa and correct-
ione have been introduced. In the authore' opinion~ thie book can serve
as a textbook for the training or apecialization of AES engineering and
technical personnel working both on the operational exploitation of WER-
type reactors and their different systems, and in laboratories with the
appropriate profiles. It is also useful to students with power engineering,
physicotechnical and engineering physics apecialities in WZ's and those "
attending power engineering tekhnikums.
The authors wish to express their gratitude to Doctor of Technical Sciences
S.A. Skvortsov for the council he provided when this book was being re-
- viewed.
TABLE OF CONTENTS
Page ~
Foreword . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -
- Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Chapter 1. Nuclear-Physics Principles of WER~s . . . . . . . . . . . 9
1.1. Fission of Heavy Nuclei . . . . . . . . . . . . . . . 9
1.2. Nuclear Tranformations of Isotopes of Uranium and
Trana-Uranic Elements . . . . . . . . . . . . . . . . . . . . . 12
1.3. Sources of Ionizing Radiation in a Reactor Unit 17
Chapter 2. Neutron-Physics Characteristics of a WER~s Reaction
Zone . . . . . . . . . . . . . . . . . . . . . . . . . . . 24
2.1. The Neutron Balance and the Reactivity of Reactors 24
2.2. The Neutron Spectrum in the Reaction Zone 29
- 2.3. Characteristics of Fuel Grids in Diff erent Reactor Operating
Mndes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32
2.4. Special Features of the Neutron-Physics Characteristics
of *_he WER-1000's Reaction Zone . . . . . . . . . . . . . . . . 39
Chapter 3. Start-Up Conditions fox Reactor Operation 44 -
3.1. Kinetics of a Reactor Operating o~ ~natantaneous and De~ayed ~
Neutrons . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44
3.2. Reactivity Coefficients of a Reactor . . . . . . . . . . . . . . 47
3.3. Requirements for the Control System and Shielding of a VVER 56
3.4. Starting a Reactor . . . . . . . . . . . . . . . . . . . . . . . 64
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Chapter 4. Neutron-Physics Cht~xactexiet~.cs of the React~.on Zone
~ During Oper~tion of a Reactor Under Poarer
4.1. DisCribution of Energy Release in the Reaction Zone . . 71
4.2. Change in a Reactor's Reactivity During Operation Under Power . 77
- G.3. Regulation Pnd Maneuverabillty of a WER . . . . . . . . . . . , 88 ,
Chapter 5. Thermohydraulic Operating Modes of a Rceactor TJnder Power 94
5.1. Heat Transfer From the Fuel Elements to the Water 94
5.2. Hydraul3c Character3st~,cs of Fuel Cartr3dges and the Reactor . 97
5.3. Perm:~s~�ible Leve1 of the Power of Fue~ Elements, Cart.ridges
and the Reactor . . . . . . . . . . . . . . . . . . . . . . . . 107
~ 5.4. Determining the Thermal Power of a Reacior . . . . . . . . . . 114
5.5. Heat Discharge of a Reactor in rhe Normal and Transient Modes . 120 -
5.6. Efficiency of an AES Power Unit W3th a VVER 126
5.7. Limitations on the Permissible Power of a Reactor That Are
Related to the Main Circulating Pump's Power Supply System 131
Chapter 6. Reactor Shutdown Modes . . . . . . . . . . . . . . . . . 137
6.1. Shutting Down a Reactor . . . . . . . . . . . . . . . . . . . . 137
6.2. Ineuring Heat Dissipation After Shutdown of a Reactor 144
- Chapter 7. Nuclear Fuel Utilization Conditions . . . . . . . . . . . 151
- 7.1. Completing Fuel Aasemblies in the Reaction Zone 151
7.2. Calculating a Reactor's Neutron-Physics Characteristics 159
7.3. Calculating the Distribution of Energy Release in Fuel
Assemblies . . . . . . . . . . . . . . . . . . . . . . . . . . 168
Appendix. Example of the Calculation of the Fuel Charge
(Recharge) in the WER-440 Reactor . . . . . . . . . . . . 174
Chapter 8. Working Capacity of WER Fuel Elements 179
8.1. Properties of Uranium Dioxide and Zirconium Alloy Fuel Element
Shells . . . . . . . . . . . . . . . . . . . . . . . . . . . . 179
8.2. Evaluating the State of Fuel Elements in an Operating Reactor . 184
f~.3. Monitoring the Hermetic State of Fuel Element Shells in a Reactor
That Has Been Shut Down . . . . . . . . . . . . . . . . . . . . 190
8.4. Studying Spent Nuclear Fuel in a HigYlly Radioactive Chamber 191
Chapter 9. Working Capacity of the Structural Materials for the
Equipment and the Water and Chemical Condi.tions in Circuit
1 of a Reactor . . . . . . . . . . . . . . . . . . . . . 196
9.1. Requirements for the Materials in Circuit 1.......... 196
9.2. Features of the Water and Chemical Conditions in Circuit 1.. 200
9.3. Methods for Controlling the Quality of the Water in Circuit 1. 201.
9.4. Purification of the Water in Circuit 1 . . . . . . . . . . . . 205
9.5. Treatment and Burial of Liquid Radioactive Wastes e.. 211
9.6. Monitoring the State of the Equipment MaCerials in Reactor
Units . . . . . . . . . . . . . . . . . . . . . . . . . . . . 213
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Chapter 10. VVER Safety , , , , , , , , , , , , , , , , , , , , , , 223
1~.1. An Approach to the Problem of Safety . . . . . . . . . . . . 223 -
10.z. Radiation Safe~y During Normal Reactor Operat3on 224
10,3. Insuring Radiation Safety Dur~ng Operationa With Fuel
Asaemblies . . . . . . . . . . . . . . . . . . . . . . . . . 226
10.4. The Most Probable Reactor Emergenc3es . . . . . . . . . . . . 229
10.5. Evaluating the Possible Energy Release During an Emergency . 235
10.6. SafeCy and Shielding Devtces . . . . . . . . . . . . . . . . 237
Chapter 11. Features of the Operation of a Power Unit With a WER--
1000 Reactor . . . . . . . . . . . . . . . . . . . . . 242
, 11.1. The Reactor Unit . . . . . . . . . . . . . . . . . . . . . . 242
11.2, The Steam-Turbine Un3.t . . . . . . . . . . . . . . . . . . . 248
_ 11,3. The Monitoring, Control and Sh3.eld~ng System 254
Chapter 12. Operational Economy of an AES With a WER 258
12.1. Cost of Electricity Produced by an AES . . . . . . . . . . . 258 _
12.2. Operating Mode and Tndicators of an AES in an Electric
Power System . . . . . . . . . . . . . . . . . . . . . . . . 265
12.3. Methods for Tncreasing the Degzee of Nuclear Fue1 Combustion
and the Duration of a Reactor's Operating Period 271
12.4. Utilization of Spent WER Fue1 . . . . . . . . . . . . . . . 274
12,5. Reducing Neutron Losses in a Reactor. . . . . . . . . . . . . 277
Bibliography . . . . . . . . . . . . . . . . . . . . . . . . . . . . 280
Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 286
' COPYRIGHT: Izdatel'stvo "Ato~~zdat," 1979 -
[45-11746]
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- CSO: 1861
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OUTLOOK FOR DEVELOPING A NUCLEAR SINGLE-LOOP HELIUM TURBINE SYSTEM WITH
- A HIGH-TEMPERAT[1RE REACTOR OF ONE MILLION kWe POWER
Moscow ENERGOMASHINOSTROYENIYE in Ruesian No 2, Feb 80 p 45
[Text] At a joint meeting of the section of nuclear machine buildtnQ,
gas turbines and compressors [of the Scientific and Technical Council
of the USSR Ministry of Power Machinery] reports were considered on the
prospects for developing po~ier units in nuclear electric plants with
single-loop helium turbine facilities and high-temperature reactors
[HTGR] with unit power of one million kWe or more. An analysis of non-
Soviet material has demonstrated the feasibility of producing helium-
cooled high-temperature nuclear reactors in the near future with pre- .
etressed ferroconcrete enclosures having a power of 2000-3000 MWt with
helium parameters of up to 1000�C and S-8 MPa at the output.
dver the past ten years in the Soviet Union and other industrially de-
- veloped countries, experimental industrial research has been in progress
on developing power facilities with HTGR reactors and single-loop helium
turbine facilities. In West Germany, an experimental facility with an
AVR reactor has been in operation on which a stable helium temperature -
of 950�C has been achfevec. at the reactox output, and a helium gas
turbine installation is in operation in Oberhausen with a non-nuclear
heat source. This facility has a power of 27 MW. ;
~ The most suitable type of reactor for a nuclear gas turbine facility is a
thertnal reactor with spherical fuel elements and one-time passage of the
thermal neutrons through the core. This gives a helium temperature of ;
850-950�C at the reactor output and high volumetric density of the heat
_ flux in the core at permissible temperatures of the ceramic nuclear fuel.
At such helium parameters, the most effective power plant is either a
single-loop gas turbine facility in which the working fluid is the helium
coolant, or a combined helium-steam plant. When the helium temperature ~
at the inlet to ~he gas turbine facility is of the order of 950�C, an ,
efficiency of at least 45% can be achieved, i. e. 1.5 times as high as
in conventional nuclear power plants with water-water reactors, and the -
the fuel component of electric power production can be considerably
reduced.
10
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With this arrangement, an integrated configuration of the ~ntire complex
of helium gas turbine facilitiea is possible with accommodation in
cavities formed in the prestressed ferroconcrete enclosure, resulting
in improved nuclear safety and operational reliability, and a reduction
in the coat of an inatalled kilowatt-hour of nuclear electric plant power
by 10-15% aa compared with HTGR facilities with two-loop steam-turbine
plante. According to apecifications for ensuring nuclear safety of the
plant, there should be at least two helium turbogroups, which means
that each should have a minimum power of about 500 MWe. The optimum.
design for the nuclear gas turbine facility is as follows: a single-
shaft facility with horizontal ahaft placement, speed of 3000 rpm,
intermediate cooling of helium with compressi~n and degree of heat
regeneration of 90%.
An appreciable enhancement of the efficiency of the nuclear electric
plant (3-5%) with gas turbine facility can be achieved by using a gas
turbine facility of the simplest cycle in the steam-gas unit, ~~ith
- generation of electric power both in a generator of~ the gas turbine
plant, and in a generatorless steam-turbine facility.
The choice of the fundamental scheme of the nuclear electric plant with
HTGR and nuclear gas turbine facility must be made with consideration of
- technical-economic indices of different modifications by specialists in
the field of reactor design and gas-turbine construction. The results
of present-day studies show that impurities in helium a.ffect reactor and
gas turbine materials. At a temperature of less than 600�C, helium ha~
little effect on these materials, but serious research will be needed
in the field of alloys based on molybdenum and niobium to reach a tem-
perature of 1000�C. Research is being done on materials and technology
for getting the necessary parameters of nuclear gas turbine plants, and
the results can be iised for the engineering design.
In nuclear facilities~with HTGR and nuclear gas turbine facilities, a dry
cooling tower can be used with reduced flowrate of circulation water, and -
also takeoff of heat from the heat exchangers for district heating pur-
poses, all of which is conducive to a further improvement of economy.
_ The development of such facilities is preceded by a complex of experi-
mental and developmental research on the HTGR and helium turbine plants:
construction and elaboration oF experimental facilities with HTGR and
- full-scale helium turbine facility with a non-nuclear heat source,
, research on developing materials for helium ~urbines and the like.
_ Based on the reports that were heard and on the discussion of the ~oint
session, it has been reco~nended that with consideration of the benefit
to be realized by the national nconomy of the nation as a result of im-
proving the economic and ecological indices of nuclear electric plants,
and taking account of the considerable technical and organizational
complexitiQS of solving this problem, more research should be done on
11
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closed-cycle gas turbine facilities using helium with HTGR reactors with
unit power of a million or more kilowatts, with helium temperature at
the reactor outlet or .>50-950�C. .It ie advisable to begin work on a
helium gas turbine plant with development of a full-acale model of an
experimental single-shaft gas turbine facility, testing it at reduced
preesure with conventional [non-nuclearJ heating of the helium on a stand
with horizontal shaft at 3000 rpm.
[8144/0983-6610]
COPYRIGHT: Izdatel'stvo "Mashinostroyeniye", "Energomashinostroyeniye", -
19 80 -
6610
CSO: 8144/983
7.2
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NON-NUCLEAR ENERGX
- UDC [621.181:628.165]:629.12
STEAM-GENERATING UNI.TS O~ERAT~NG ON $EA WATER
Leningrad PAROGENERATORNYYE USTANOVKT NA MOR~KOY VODE in Russian 1979
pp 2, 230-232
[Foreword and table of contents frot~ the book "P~rogeneratornyye Ustanovki
na Morakoy Vode" by Leonid Tllarionovich ~en' and Yur3y Vladimirovich
Yakubovskiy, Izdatel'stvo Sudostroyeniye, Leningrad, 1979, signed to press
13 June 1979, 3,700 copies, 232 pagea]
[Text] FOREWORD
The development of heat- and power-engineering units must proceed along the
line of reducing the effect of production technology on the environment
and increasing their economic effectiveness. At the present time the analysis
of power-engineering units is, as a ru1e, lim~.ted to a diacussion of the
thermal efficiency of equipment and machinery without taking into considera-
tion the nature of the output, the amount of water consumed, and the pol-
lutants released into the atmoephere.
However, as a resul~ of the increase in the amount of water consumed during
the production process, some approach to the question of using sea water
is required. In particular, it is advisable to develop new units that are
capable of operating on polluted or sea water. Under conditions of limited
natural fresh water sources, such units should insure the production of
fresh water in a quantity sufficient for technological requirements without -
increasing fuel consumption.
There is almost no literature on planning and design3ng elements of power-
engineering units operating on sea water, und this book is the first attempt
to develop techniques for designing the thermal systems of steam-generating
and recovery units that operate with sea water.
L. I. Sen' wrote Section 1.1, Ch�;ter 2, Sections 3.3-3.5, 4.2, 5.5-5.8,
6.2-6.5 and the appendices; Yu.V. Yakubovskiy wrote Sections 1.2-1.6,
5.1-5.4 and 6.1; L.I. Sen' and Yu.V. Yakubovsky, together with V.V. Permyakov,
wrote Sections 3.1 and 3.2; L.I. Sen' and V.G. Dobrozhanskiy wrote Sections
4.1, 4.3 and 4.4. L.I. Ser_' was responsible for the overall editing of
the manuscript.
13
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The authors url.sh to express the~r heartfelt thanks and gratitude to Pro-
fessor A.M. Podsushnyy for a number of valuable methodological instructions
in the preparation of this book, and ProfeRSOr N.V. Golubev for his criti-
cal remarka and recommendations on selecting materials for it.
TABLE OF CONTENTS
Page
Foreword . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Sycnbole . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Chapter 1. Designs of Water Distillation Units With Pellicular Heat -
Exchangers . . . . . . . . . . . . . . . . . . . . . . . . 6
1.1. Analysis of Steam and Water Consumption on Board Ships 6
1.2. Ship Water Distillation Unit Designs . . . . . . . . . . . . . . 9
1.3. Pellicular Evaporators and Heate.�rs . . . . . . . . . . . . . . . 15
1.4. Variants for Modernizing Distiilation Units . . . . . . . . . . 19
1.5. Using Contact Distillation Units to Prevent Marine Pollution
by Pstroleum Products . . . . . . . . . . . . . . . . . . . . . 27
Chapter 2. Thermal Systems of Steam-Generating Units Operating on
Sea Water . . . . . . . . . . . . . . . . . . . . . . . . . 30
2.1. Purpose of Steam-Generating Units . . . . . . . . . . . . . . . 30
2.2. Thermal Systems for Producing Operating Steam and Fresh Water
. From Sea Water in Ship Power Plants . . . . . . . . . . . . . . 33
2.3. High-Temperature Heating of Sea Water . . . . . . . . . . . . . 37
2.4. Plans of Steam-Generating Uxiits Operating on Sea Water 43
2.5. Comparative Analyais of Thermal Systems . . . . . . . . . . . . 52
2.6. Operating Conditions and Parameters of Thermal Systems 57 -
2.7. A Water Treatment System . . . . . . . . . . . . . . . . . . . . 70
Chapter 3. Heat- and Mass-Exchange Processes in Pellicular Devices . 74
3.1. Characteristics of a Pellicular Flow of Liquid 74
3.2. Movement and Heat Exchange of a Liquid Film in Equipment 83
3.3. Heating a Liquid Film From an E~uitting Source 94
3.4. Heat-and Mass-Transfer Processes in a Laminar, Draining Liquid
Film . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108
3.5. Heat Exchange in a Turbulent Film . . . . . . . . . . . . . . . 130
Chapter 4. Scale Formation Pxocesses Dur3ng the Heat~ng and
Evaporation of Sea Water in Heat Exchange Units 132
4.1. Scale Formation During the Heating and Evaporation of Sea Water. 132
4.2. Calculating Ion Equilibriums in Sea Water Durfng Thermal _
- Transformations . . . . . . . . . . . . . . . . . . . . . . . . . 142
4.3. Selecting a Sea Water Treatment Method ~n Order to Avoid Scale
Formation in Heat Exchange Units . . . . . . . . . . . . . . . . 151
4.4. Analysis of the Perfor~ance of Experimental Antiscale Devices . 160
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Page
Chapter 5. Techn~.ques for Designing Pellicular Devices Operat3ng
on. ~ea Water . . . . . . . . . . . . . . . . . . . . . . 172
5.1. Calculating the Heat-Exchange Surface in Pellicular Evaporators. 172
5.2. Selecting and Designing Intake and Outlet Devices for a Film 180
5.3. Selecting and Designing Separation Units . . . . . . . . . . . . 185 -
5.4. Determining the Hydraulic Resistance of a Pellicular Evaporator. 188
5.5. Designing a Pellicular ContacC Heater-Acidifier 190
5.6. Deaigning a High-Temperature Sea Water Heater and Evaporatnr 191
Chapter 6. Technical and Economic Tndicators and Prospects for the
Use of Units . . . . . . . . . . . . . . . . . . . . . . . 195
6.1. Effectiveness of the Utilization of Pellicular Evaporating
Units . . . . . . . . . . . . . . . . 195
. . . . . . . . . . . . .
6.2. Steam-Generating Units for Floating Fish-Processing Plants 197
6.3. Recoumiended Plans for Steam- and Power-Engineering Units 201
6.4. Protecting the Environment From Pollution During the Use of
Steam-Generating Units Operating on Sea Water . . . . . . . . . 205 -
6.5. Prospective Plaiis for Steam- and Gas-Generating Units 208
6.6. Principles of the Organization of a Closed Water Supply System _
_ for Fi~h-Processing Vessels . . . . . . . . . . . . . . . . . . 211
6.7. Prospective Methods for ~urify3,ng Dxainage Water on Fish-
Processing Vessels . . . . . . . . . . . . . . . . . . . . . . . 215
_ 6.8. A Syatem for Closed Water Utilization on Fish-Processing
Vessels P1ith Complete Neutralization of the Waste and Bilge
Waters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 216
- Appendix �1. Sea Wate~r Compoeitivn ~ables . . . . . . . . . . . . . . 220
Appendix 2. Water Absorption Coefficients of Gasses 222
Appendix 3. Thermophysical Properties of Water . . . . . . . . . . . 223
Appendix 4. Formulas for Determin~.ng the Thermophysical Properties of
- Sea Water as a Funct~on of the Salt Concentration, Pressure
- and Temperature . . . . . . . . . . . . . . . . . . . . . 224
Appendix S. Programs for Calculating Enthalpy and the Logarithm of a
Gas Mixture's Relative Pressure, as a Function of the
Temperature, on Minsk-2~2 and AKI-T Computers 224
Bibliography . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 226
COPYRIGHT: Izdatel'stvo "Sudostroyeniye," 1979
[44-11746]
11746
CSA: 1861 15
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UDC 621.51-52
SYST~M ~'~R THE ~VERALL AUTOMATION OF COMPRESSOR STATIONS
Moscow PROMYSHLENNAYA ENERGETIKA in Russian No 10, 1979 pp 31-33 _
BOGOSLOVSKIY, YU. S., SHAYKHUTDINOV, G. G. and VERBITSKIY, A. M.,
State Institute for the Design and Planning of Mine Cc~nstruction in the
Southern Regions of the USSR .
[AbatractJ The recently developed UKAS system for~.the turbocompressors in
the K100-K500 seriea manufactured by the Khabarovsk Energomash Plant
- represents a highly effective and reliable automation package which pro-
duces considerable savings by replacing relay-contact equipment with its
contactless counterparts, incorporating more sophisticated design features,
and assuring more extensive cox~trol and monitoring of compressor-station
facilities. The system is based on programmed control of the parallel-
connected operat~.ng cycle of a multip~e-unit compressor station. It
assures a turbocompressor start-up time of 30 minutes underload. A block
diagram of the system is presented. The UKAS package consists of two sub-
packages: UKAS-A (ShKh-9102-53A3 type control bay, a ShES-9006-OOA2 type
' contxol panel section and a process monitoring panel, delivered by the
- Enexgomash Plant in tandem with series K100-K500 ccrmpresaors); and UKAS-
5(ShES-9103-83A3 type auxillary drive bay and ShES-8801-OSA3 monitoring =
bay, also delivered b} the Energomash). Figure l.
[22-1386]
- ~6
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M~CHAN~CS OF SOLTDS
- UDC 625,03
VIBRATION ANiD THE STRENGTH AND STABILTTY Q~ COMPZ~X MECHANTCAL 3YSTEMS
Kiev KOLEBANTXA, PROCHNO$T' T USTOYCHTVOST' SLOZHNYKH MEKHANTCHESKIKH
~ SISTEM in Russian 1979 pp 2, 155-156
[Annotation and table of contenta from the collection of works "Kolebaniya,
Prochnost' i Ustoychivost' Slozhnykh Mekhanicheskikh Sistem," edited by
L. Ye. Borodyanskiy and T.V. Katsovenko, Dnepropetrovsk Department, In-
atitute of Mechanics, Ukra3n3an SSR Academy of Sc~encea, Izdatel'stvo
Naukova Dumka, Kiev, 1979, s~.gned to press 4 April 1979, 1,550 copies,
163 pages] -
- (Text] ANNOTATION
The articles in this collection axe based on the xesults of theoretical and -
- experimental research on the dyn~cs and strength of complex linear and
nonlinear mechanical systema. In a nunibe~ of articles the authors explain
methods for solving the problema involved in optimizing the parameters of -
dynamic systems and identifying fihem. Tn many cases the research has been
done with due consideration for the random nature of actual external in-
fluences. Steady-state and transient ~notion mode~, including those in-
fluenced by short-term effecte, are analyzed.
This book is intended for scientific, eng~neering and technical woxkers
concerned with problems of applied taechan~.cs~ machine build~~g and trans-
portation.
TABLE OF CONTi:NTS
Page
An Experimental Test of the Results of Investigations of the ' -
Stability of the Curvilinear Motion of Railway Carriages
(V.A. Lazaryan, V.I. Zinchenko, Yu.V. Demin, N.A. Radchenko) 3
Stability of the Curvilineax' Mot~,on ~nd Tnduced V~lbrat~ons of -
High-Speed Railway Carriages
(N.A. Radchenko) . . . . . . . . . . . . . . . . . . . . . . . . 10
~.7
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Page
Determining the Area of Rational Parameters of Mechanical Systema From
the Condition of Dynamic Stability . . . . . . . . . . . . . . . . 18
Investigation of the Effect of Variability of the Pseudoslip Co-
efficient on the Dynamic Stability of Railway Carriages
(N . S . Olemskaya) . . . . . . . . . . . . . . . . . . . . . . . . . 22
Evaluating the Aerodynamic Stability of a Suspended Crossing
(M.I. Kazak.evich) . . . . . . . . . . . . . . . . . . . . . . . . 29
Lowering the Order of the Nonautonomous Differential Equations of Motion
of Systems With Substantial Nonlinearities
- (O.M. Ratnikova) . . . . . . . . . . . : . . . . . . . . . . . . . 33
Automatic Selection of the Integration Step During the Solution of the
Initial-Value Problem for Normal Differential Equations
(I.A. Zil'berman) . . . . . . . . . . . . . . . . . . . . . . . . 36
Identifying Rigidity and Dry Friction in Elements of Multimass Mechanical
Systems
(V.F. Ushkalov, V.P. Shabel'skiy) . . . . . . . . . . . . . . . . 40
Identifying the Rigidities of Mechanical Systems by Their Natural
_ Freuquencies
( S . F . Red' ko ) . . . . . . . . . . . . . . . . . . . . . . . . . . . 46
A Method for Decomposing the Problem of Tdentifying Mechanical Systems
(S.F. Red'ko, V.P. Yakovlev) . . . . . . . . . . . . . . . . . . . 49
On Mathematical Models for Tnvestigating the Non-Steady-State Movement
Modes of Trains With Tank Cars
(V.A. Lazaryan, G.I. Bogomaz, N.M. Khachapuridze) . . . . . . . . 57
Determining the Associated Masses of a Liquid in a Partially Filled,
Horizontal, Cylindrical Cavity
(G.I. Bogomaz, A.V. Krasnikov, L.V. Shcherbak) . . . . . . . . . . 72 _
Determining the Displacement Potential of a Liquid in an Elastic Shell
(R.D. Krasn3.kova) . . . . . . . . . . . . . . . . . . . . . . . 76
Exper~mental Investigation of the Load on a Horizontal Cylindrical
Shell Containing a Liquid Upon Tmpact With an Obstacle
(Ye. T. Grigor'yev, A.V. Krasnikov, I,.V. Shcherbak) 81
Mathematical Modeling of the Motion of a Train of Conveyor Be=cs
(V.A. Lazaryan, N.Ye. Naumenko, N.M. Khachapuridze) . . . . . . . 85
18
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Page -
Induced Vibrationa of Systema With Dry Friction
(L.A. Dlugach, N.V. Dontsova) . . . . . . . . . . . . . . . . . . . 92
Free Longitudinal Vibratione of Parallel Rode Tha~.t Are Connected
Elastically
(N.Ye. Naumenko) . . . . . . . . . . . . . . . . . . . . . . . . . . 95
Investigation of the Effect of the Parameters of Elastic Wheels on the
Vertical vibrations of a Subway Ca~r
(I.A. Mashchenko, L.M. Reznikov, Ye.Yu. Trubitskaya) . . . . . . . 101 .
Special Features of the Investigation of the Resistance to Vibration of
Elastic Designs With Due Consideration for Frequency Factors
(N.I. Voytsekhovskiy) . . . . . . . . . . . . . . . . . . . . . . . 110
Shock Absorption in Engineering Structures During Impact Loading
(I.G. Barbas) . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 ~
- The Optimal Relationship of a Shock Absorber's Force Coefficient of
Nonelastic Resistance to the Size of Its Path
(L. A. Manashkin) . . . . . . . . . . . . . . . . . . . . . . . . . 119
Impact Loading of Engineexing Structurea by a Free-Flowing Weight
(I.G. Barbas) . . . . . . . . . . . . . . . . . . . . . . . . . . . 123
Vibrations of a Dynamically Nonsymmetrical Design Acted Upon by
Multipaint Excitation -
(V . N . Taranenko) . . . . . . . . . . . . . . . . . . . . . . . . . 127
Addition of the Vibrators' Forces During Multipoint Excitation of a
Deaign
(I.Ye. Kovalev, V.N. Taranenko) . . . . . . . . . . . . . . . . . . 132
Vibrations of a~n Infinitely Long Beam Lying on an Elast3.c Base With
~ao Characteristics, When Acted Upon by a Moving Harmonic Load
(V . D . Danovich) . . . . . . . . . . . . . . . . . . . . . . . . . . 135
On the Forces in a Carriage-Rail System at Above-Critical Speeds
(T.F. Mokriy) . . . . . . . . . . . . . . . . . . . . . . . . . . . 141
On the Existence of Limited Realizations of Random Processes With a
Given Spectral Density ~
(Ye.T. Grigor'yev, V.V. Migur) . . . . . . . . . . . . . . . . . . 145
19
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. Page
- Determining the Correlat~on Macnents of the Coord~nates of a
Multimass System in Connect~.on FMth Non-Steady-State, Random
Kinematic Perturbations
(L.M. Reznikov) . . . . . . . . . . . . . . . . . . . . . . . 147
COPYRIGHT: Izdatel'stvo "Naukova Dumka," 1979
[43-11746]
11746
- CSO: 1861
-END-
20
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