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AbstractAbstract
[en] The paper gives an account of experience collected during the 4 years of operation of the BOR-60 reactor and after its shutdown due to defective fuel assemblies. Most of the experience relates to the radiation situation a) during operation with completely intact and partly defective fuel assemblies b) after reactor shutdown c) during rearrangement of fuel elements and refuelling, d) during maintenance work in large structural components. Information is also given on the types of radioactive isotopes in the fallout deposits and their local distribution as well as on the measured radioactivity. (GG/AK)
[de]
Es wird ueber Erfahrungen berichtet, die waehrend des 4-jaehrigen Betriebes des BOR-60 Reaktors und nach seiner Stillegung infolge schadhaft gewordener Brennelemente gemacht wurden. Die Erfahrungen betreffen insbesondere den Strahlungszustand a) waehrend des Betriebes mit voellig intakten und teilweise schadhaften Brennelementen, b) nach Stillegung der Anlage, c) bei Umladungs- und Neubeschickungsarbeiten und d) bei Instandsetzungsarbeiten an Grossausruestungen. Es werden Angaben gemacht ueber die Arten der sich ablagernden radioaktiven Isotope und deren oertliche Verteilung sowie ueber die auftretenden Radioaktivitaeten. (GG)Original Title
Bedienung der Ausruestung des mit Schnellbrueter BOR-60 ausgeruesteten Kraftwerkes bei Bestrahlung
Primary Subject
Source
1 fig.; 2 tabs. Translated from At. Ehnerg. (Dec 1974) v. 37(6) p. 471-474.
Record Type
Journal Article
Journal
Archiv fuer Energiewirtschaft; v. 29(4); p. 383-390
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Obsluzhivanie oborudovaniya AEhS BOR-60 v radiatsionnykh usloviyakh
Primary Subject
Source
For English translation see the journal Sov. J. At. Energy.
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; v. 37(6); p. 471-474
Country of publication
AEROSOLS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BREEDER REACTORS, COLLOIDS, CONTAMINATION, DAYS LIVING RADIOISOTOPES, DISPERSIONS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EVEN-ODD NUCLEI, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, INFORMATION, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIQUID METAL COOLED REACTORS, MAINTENANCE, NUCLEAR FACILITIES, NUCLEI, OPERATION, POWER PLANTS, POWER REACTORS, RADIOISOTOPES, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, SOLS, THERMAL POWER PLANTS, XENON ISOTOPES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Gryazev, V.M.; Krasnoyarov, N.V.; Kevrolev, V.P.; Kondrat'ev, V.I.; Nechaev, B.N.; Smirnov, A.M.
Fast reactor power stations, proceedings of the international conference organized by the British Nuclear Energy Society held on 11-14 March, 1974 at the Institution of Civil Engineers, London1974
Fast reactor power stations, proceedings of the international conference organized by the British Nuclear Energy Society held on 11-14 March, 1974 at the Institution of Civil Engineers, London1974
AbstractAbstract
No abstract available
Primary Subject
Source
British Nuclear Energy Society, London; p. 21-26; ISBN 0727700014; 
; 1974; Thomas Telford; London; International conference on fast reactor power stations; London, UK; 11 Mar 1974
; 1974; Thomas Telford; London; International conference on fast reactor power stations; London, UK; 11 Mar 1974
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Some results of continuous long-time operation of the BOR-60 nuclear power plant are summarized. The power plant was brought to power in December, 1949. During the operation fuel elements of different types were tested under high loads and temperatures (fuel burnup of 12 per cent was achieved). Absorbing materials for control and safety rods, the main and auxiliary equipment, the steam generator design were also tested. The stationary, transient and energency conditions were investigated, sodium technology was worked out (under maintenance conditions, in particular). The obtained experience may be used for development of future fast reactors
Original Title
Osnovnye rezul'taty ehkspluatatsii ustanovki BOR-60
Primary Subject
Source
For English translation see the journal Sov. J. At. Energy.
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; v. 38(3); p. 131-134
Country of publication
ACCIDENTS, BOILERS, BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, MAINTENANCE, OPERATION, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, TESTING
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Aristarkhov, N.N.; Bets, N.I.; Efimov, I.A.; Filonov, V.S.; Kevrolev, V.P.; Rybakov, V.N.; Skvortsov, S.A.
Fast reactor power stations, proceedings of the international conference organized by the British Nuclear Energy Society held on 11-14 March, 1974 at the Institution of Civil Engineers, London1974
Fast reactor power stations, proceedings of the international conference organized by the British Nuclear Energy Society held on 11-14 March, 1974 at the Institution of Civil Engineers, London1974
AbstractAbstract
No abstract available
Primary Subject
Source
British Nuclear Energy Society, London; p. 515-523; ISBN 0727700014; ; 1974; Thomas Telford; London; International conference on fast reactor power stations; London, UK; 11 Mar 1974
; 1974; Thomas Telford; London; International conference on fast reactor power stations; London, UK; 11 Mar 1974
Record Type
Book
Literature Type
Conference
Country of publication
ALKALI METALS, BREEDER REACTORS, ELEMENTS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FLUIDS, LIQUID METAL COOLED REACTORS, METALS, PLUTONIUM REACTORS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SODIUM COOLED REACTORS, TEST REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Gryazev, V.M.; Krasnoyarov, N.V.; Kevrolev, V.P.; Afanasiev, V.A.; Efimov, V.N.
Proceedings of the international symposium on physics of fast reactors1973
Proceedings of the international symposium on physics of fast reactors1973
AbstractAbstract
No abstract available
Primary Subject
Source
Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan); p. 200-214; 1973; Power Reactor and Nuclear Fuel Development Corp; Tokyo, Japan; International symposium on physics of fast reactors; Tokyo, Japan; 16 Oct 1973
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Some design features of NPPs with the RBMK-1000 reactors and results of their operation are considered. The RBMK-1000 reactor is a serial power 1000 MW uranium-graphite boiling water cooled reactor. From December, 1973 till December, 1981 eight power units with RBMK-1000 reactors were brought up to operation at rated power. In the full volume of the starting minimum, the power units can be constructed during 16-18 months. The basic NPP units can be brought up to the nominal powers during 8-10 months, and the subsequent units - during 6 months. The mean annual installed power factor of a NPP is 73-74%. Eight years of successful operation of a power unit with RBMK-1000 confirmed high working capacity of the reactor and basic power plant equipment and revealed the design reserves. This permitted to increase its electric power up to 1500 MW at the expense of heat exchange intensification in the core without modification in design. The RBMK-1000 reactor is one of the main reactor types for the development of the nuclear power engineering in the USSR
Original Title
Nekotorye osobennosti i opyt ehkspluatatsii AEhS s RBMK-1000
Primary Subject
Source
For English translation see the journal Soviet Journal of Atomic Energy (USA).
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; ISSN 0004-7163; ; v. 54(4); p. 257-262
; v. 54(4); p. 257-262
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Le reacteur experimental rapide BOR
Primary Subject
Record Type
Journal Article
Literature Type
Progress Report
Journal
Energie Nucleaire (Paris); v. 12(1); p. 33-38
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kazachkovskii, O.D.; Gryazev, V.M.; Krasnoyarov, N.V.; Kevrolev, V.P.; Afanasiev, V.A.; Smirnov, A.M.; Kondrat'ev, V.I.
Proceedings of the Indo-Soviet seminar on fast reactors, Reactor Research Centre, Kalpakkam, December 6-8, 19721974
Proceedings of the Indo-Soviet seminar on fast reactors, Reactor Research Centre, Kalpakkam, December 6-8, 19721974
AbstractAbstract
No abstract available
Primary Subject
Source
Department of Atomic Energy, Bombay (India); p. 181-201; 1974; Department of Atomic Energy; Bombay; Indo-Soviet seminar on fast reactors; Kalpakkam, India; 6 Dec 1972; 3 refs., 8 figs.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kazachkovskij, O.D.; Gryazev, V.M.; Krasnoyarov, N.V.; Kevrolev, V.P.; Afanas'ev, V.A.; Smirnov, A.M.; Kondrat'ev, V.I.
Engineering of fast reactors for safe and reliable operation1973
Engineering of fast reactors for safe and reliable operation1973
AbstractAbstract
No abstract available
Original Title
Nekotorye voporosy oberpecheniya bezopasnoj ehkspluatatsii reaktora BOR-60
Primary Subject
Secondary Subject
Source
Faude, D. (ed.); Bundesministerium fuer Forschung und Technologie, Bonn (F.R. Germany); Gesellschaft fuer Kernforschung m.b.H., Karlsruhe (F.R. Germany); Kerntechnische Gesellschaft im Deutschen Atomforum e.V., Bonn (F.R. Germany); International Atomic Energy Agency, Vienna (Austria). International Working Group on Fast Reactors; v. 2 p. 473-491; 1973; Gesellschaft fuer Kernforschung m.b.H; Karlsruhe, F.R. Germany; International conference on engineering of fast reactors for safe and reliable operation; Karlsruhe, F.R. Germany; 9 Oct 1972; 8 figs.; 1 tab.; 3 refs.
Record Type
Book
Literature Type
Conference
Country of publication
BREEDER REACTORS, CONVECTION, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HEAT TRANSFER, LIQUID METAL COOLED REACTORS, OPERATION, POWER REACTORS, REACTOR SAFETY, REACTOR SAFETY EXPERIMENTS, REACTOR SHUTDOWN, REACTORS, RESEARCH AND TEST REACTORS, SAFETY, SODIUM COOLED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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