Kravchenko, I.N.; Bagdasarov, Yu.E.; Likhachev, Yu.I.
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1987
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1987
AbstractAbstract
[en] Method for determining stressed-strained state of fuel cans and hexagonal fuel assembly shroud under their simultaneous deformation in a fast reactor core is presented. Mathematical formulation of thee-dimensional problem of determining equilibrium fuel element configuration in a fuel assembly is given. The solution of the problem is inportant both for strength and thermal-hydraulic analysis. Descriptions of algorithms, computing program complex and results of test calculations are presented. The developed technique and program complex enable to determine fuel element displacement inside fuel assembly and contact forces among adjoining fuel elements, corresponding to equilibrium, configuration of fuel element cluster in hexagonal fuel assembly shroud; geometric characteristics of equilibrium configuration of fuel element cluster (squares of flow sections for the coolant), necessary for thermal-hydraulic calculation of fuel assembly; stressed-strained state of fuel assembly elements (fuel cans spacing wire, shroud) under simultaneous deformation of the shroud and fuel element cluster
Original Title
Raschet na prochnost' tvehlov i shestigrannogo chekhla TVS s uchetom sovmestnogo deformirovaniya puchka tvehlov i chekhla v protsesse oblucheniya v aktivnoj zone bystrogo reaktora
Primary Subject
Secondary Subject
Source
1987; 22 p; 8 refs.
Record Type
Report
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Country of publication
BREEDER REACTORS, CONFIGURATION, COOLING SYSTEMS, DEFORMATION, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ASSEMBLIES, INFORMATION, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MECHANICAL PROPERTIES, POWER REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SODIUM COOLED REACTORS, STRESSES
Reference NumberReference Number
INIS VolumeINIS Volume
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Likhachev, Yu.I.; Vashlyaev, Yu.N.; Kravchenko, I.N.
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1980
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1980
AbstractAbstract
[en] Methods for calculating deformations and interaction forces of heat-generating assemblies (HGA) of fast reactor core with account for the effect of control and protection system (CPS) elements at the reactor operation and change of interaction efforts between HGA at the reactor shutdown, are described. The results of testing the suggested methods on example of estimate of HGA behaviour of the BN-350 reactor are presented. For estimating the effect of CPS elements on HGA bending the sector model has been used. It is assumed that HGA deformation inside each sector is independent of HGA deformation of other sectors. A higher calculation accuracy is attained by means of laying out of sectors into regions of preferable influence of emergency protection elements and compensating packets. When determining deformation and interaction efforts between HGA caused by temperature change in the course of shutdown it is supposed that the HGA deformation is purely elastic. The methods described are realized in the form of ABRI-CPS and ABRI-HOL programs written in FORTRAN for the BESM-6 computer. The results of HGA calculations of the BN-350 reactor core show that CPS elements decrease contact efforts in the middle of the central packet, increase contact efforts in the peak of the central packet, increase contact efforts in the peaks of packets from the eight row to the periphery and increase contact efforts in the middles of packets from the 5th to 9th row
[ru]
Original Title
Metod rascheta usilij vzaimodejstviya i deformatsij TVS aktivnoj zony bystrogo reaktora s uchetom vliyaniya organov SUZ i raskholazhivaniya reaktora
Primary Subject
Source
1980; 21 p; 4 refs.; 6 figs.
Record Type
Report
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INIS IssueINIS Issue
Zabudko, L.M.; Kravchenko, I.N.; Meshkov, M.N.; Bibilashvili, Y.K.; Korostin, O.S.; Ogorodov, A.N.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1987
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1987
AbstractAbstract
[en] Deformations of hexagonal tubes of fuel assemblies (steel 08 Cr16Ni11MZT) and pin claddings (steel 0 Cr16Ni15MZB) from the BN-600 reactor are examined after irradiation at a maximal dose of about 70 DPA. Effects of radiation dose at 430-4500C on swelling, temperature dependence of creep, fuel can diameters are determined
[fr]
On examine apres irradiation dans le reacteur BN-600 la deformation des tubes hexagonaux des assemblages combustibles (acier 08Cr16Ni11MZT) et des gaines des aiguilles (acier 0Cr16Ni15MZB) pour une dose maximale de 70 DPA environ. On a determine l'influence de la dose a 430-4500C sur le gonflement, la variation du fluage en fonction de la temperature et le diametre des gainesOriginal Title
Resultats des mesures et du traitement statistique des deformations dans BN-600 des tubes hexagonaux et des aiguilles en aciers austenitiques ecrouis
Primary Subject
Source
Apr 1987; 12 p; Translated from Russian from the French-Soviet seminar on fuel assemblies, Cadarache (FR), Apr 1987.
Record Type
Report
Literature Type
Translation
Report Number
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, DEFORMATION, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MECHANICAL PROPERTIES, NICKEL ALLOYS, POWER REACTORS, RADIATION EFFECTS, REACTORS, SODIUM COOLED REACTORS, STAINLESS STEELS, STEELS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Buksha, Yu.K.; Zabudko, L.M.; Kravchenko, I.N.; Matveenko, L.V.; Meshkov, M.N.
Specialists' meeting on predictions and experience of core distortion behaviour, Wilmslow, England, 1-4 October 19841984
Specialists' meeting on predictions and experience of core distortion behaviour, Wilmslow, England, 1-4 October 19841984
AbstractAbstract
[en] An approach to assessment of fast reactor fuel assembly performance has been considered. A concept of passive restraint of fuel assemblies in a reactor adopted in the USSR is described. Some methods for calculating the interassembly interactions during operation are briefly outlined, some calculated results are presented. A problem of fuel assembly performance during refuelling taking into account the refuelling line capabilities is considered. Some results from fuel assemblies operation experience in the BN-600 reactor are given. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria). International Working Group on Fast Reactors; UKAEA Headquarters, London; National Nuclear Corp. Ltd., Risley (UK); 382 p; Oct 1984; p. 77-98; Specialists' meeting on predictions and experience of core distortion behaviour; Wilmslow (UK); 1-4 Oct 1984; 7 figs, 1 tab.
Record Type
Report
Literature Type
Conference
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Zabudko, L.M.; Kravchenko, I.N.; Korostin, O.S.; Ogorodov, A.N.
Fast reactor core and fuel structural behaviour1990
Fast reactor core and fuel structural behaviour1990
AbstractAbstract
[en] The paper presents results of the analysis of data on the deformation of the BN-600 reactor irradiated fuel subassemblies hexagonal ducts which are made of austenitic cold-worked and ferritic-martensitic steels, and of data on the deformation of fuel pin cladding which is made of austenitic cold-worked steels. Some results of subassemblies withdrawal force measurements are also presented. (author)
Original Title
Deformation in irradiated fuel subassemblies of a liquid metal cooled fast breeder reactor
Primary Subject
Source
British Nuclear Energy Society, London (United Kingdom); 326 p; ISBN 0 7277 1566 6;
; 1990; p. 289-292; British Nuclear Energy Society; London (United Kingdom); International conference on fast reactor core and fuel structural behaviour; Inverness (United Kingdom); 4-6 Jun 1990

Record Type
Book
Literature Type
Conference
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Kravchenko, I.N.; Poplavskij, V.M.; Borisov, V.V.; Kamaev, A.A.; Portnyanoj, G.A; Usachev, A.B.; Chajkin, B.S.; Balsanov, A.V.; Reshitko, V.F.
Nuclear power technologies. Abstracts of reports2000
Nuclear power technologies. Abstracts of reports2000
AbstractAbstract
[en] Description of solid sanitary and technogenic waste reprocessing technology; heat diagram of heat recovery of waste reprocessing process; description of facility operation fundamental modes; requirements to basic systems and materials of facility of technogenic and sanitary industrial waste high-temperature reprocessing; standard-technical documents according to which facility designing, building and operation is conducted are presented in the report. There have been demonstrated the capability for creation of facility of high-temperature sanitary and technogenic waste recovery. There have been selected structure materials with operation lifetime of not less than 10 years at the parameters obtained in the furnace. There have been shown that systems of heat-sink cooling with sodium coolant created in atomic energetic are applicable for heat recovery of melting furnace and outgoing gases in high-temperature sanitary and technogenic waste reprocessing facilities with bubbling flux bath
Primary Subject
Source
Koltysheva, G.I.; Mukusheva, M.K.; Perepelkin, I.G. (eds.); Ministry of Energy, Industry and Trade of the Republic of Kazakhstan (Kazakhstan); Department of Energy of the United States of America (United States); National Nuclear Center of the Republic of Kazakhstan (Kazakhstan); Nuclear Technology Safety Center of the Republic of Kazakhstan (Kazakhstan); 250 p; 2000; p. 51; International seminar on nuclear power technologies; Mezhdunarodnyj seminar po tekhnologii yadernoj ehnergetiki; Astana (Kazakhstan); 14-17 May 2000
Record Type
Miscellaneous
Literature Type
Conference
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