AbstractAbstract
[en] Paper presents calculation ratios to the determine kinetics of inelastic deformation of shell and plastic sealing of WWER-1000 neutron absorption rod powder centre, considers peculiarities of neutron absorption rod loading with regard to variation of mechanical characteristics of structural materials of shell and swelling of powder absorber under effect of neutron flows, high temperature and cyclic loading. Progressing deformation of two variants of a neutron absorption rod made using O6Kh18N10T steel and EhP-630U alloy with regard to statistical spreading of parameters is studied. Estimations of a neutron absorption rod service life and of probability of destruction at reaching maximal permissible deformation of shell and maximal burn out of absorber are obtained. 8 refs., 2 figs., 3 tabs
Original Title
Veroyatnostnaya model' dlya opredeleniya resursa sterzhnevykh pehlov VVEhR-1 000
Primary Subject
Record Type
Journal Article
Literature Type
Numerical Data
Journal
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ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, DATA, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MATHEMATICAL MODELS, MECHANICAL PROPERTIES, NICKEL ALLOYS, NUMERICAL DATA, RADIATION EFFECTS, RADIATION FLUX, STAINLESS STEELS, STEELS, TEMPERATURE RANGE, TITANIUM ADDITIONS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
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Risovannyj, V.D.; Zakharov, A.V.; Klochkov, E.P.; Efremov, A.I.; Chernyshev, V.M.; Mal'stev, V.V.; Roslyakov, V.F.
Abstracts of reports of the international scientific-practical conference1996
Abstracts of reports of the international scientific-practical conference1996
AbstractAbstract
[en] For the reactors on fast neutrons in system of control and protection are used safety rods (SR), made on base enriched by isotope 10 B boron carbide in kind of hot pressed pellets. The service time of such rods is limited and after operation in reactor during appointed service life they are replaced by new rods. The fulfilling safety rods are subject to utilization and are stored in storage pools. During 1992-1993 in State Scientific Centre Research Institute of Nuclear Reactors researches of safety rods, fulfilling in reactor BOR-60 (1 rod of design 1057-0) and BN-600 (4 rods of a design 1663) and long time storing in pools of storage, were conducted. It was shown, that in rod SR 1057-0 after 537 effective days of operation in reactor BOR-60 and 18 years of storing in pool of storage was undamaged of absorbing pins, the majority of pellet B4 C have satisfactory conditions and sizes. Simultaneously essential decrease of the mechanical characteristics of absorbing pins claddings and external cover tube of rod was shown. Absorbing pins of rods design 1663, fulfilling various time in the reactor BN-600, not had of damages. Significant quantity of pellets B4 C have save integrity. Low extension part of a rod, fulfilling 330 effective days, had appreciable bent because of non-uniformity neutron influence, and the material had low fracture toughness. The absorbing pin cladding have reduced the plastic characteristics, The conclusion was made, that the resource of fast reactors safety rods is limited by decrease of the mechanical characteristics of constructional details at low part of rods. Thus the measures on increase service time of the safety rods should first of all provide use as constructional materials radiation resistant steels and alloys. Improvements in should also be introduced a design of rods, having excluding of regular influence of their low part at operation
Original Title
Materialovedcheskie issledovaniya sterzhnej AZ bystrykh reaktorov BOR-60 i BN-600 i problemy uvelicheniya ikh resursa
Primary Subject
Source
Koltysheva, G.I.; Perepelkin, I.G. (eds.); Ministerstvo Nauki-Akademiya Nauk, Almaty (Kazakstan); Minesterstvo Ehnergetiki i Ugol'noj Promyshlennosti, Alma-Ata (Kazakstan); Ministerstvo Ehkonomiki, Almaty (Kazakstan); Natsional'nyj Yadernyj Tsentr, Kurchatov (Kazakstan); Natsional'naya Aktsionernaya Kompaniya KATEhP, Almaty (Kazakstan); Nauchno-Issledovatel'skij Inst. Ehksperimental'noj i Teoreticheskoj Fiziki Natsional'nogo Gosudarstvennogo Univ., Almaty (Kazakstan); Agentstvo po Atomnoj Ehnergii, Alma-Ata (Kazakstan); Yadernoe Obshchestvo Respubliki Kazakhstan, Kurchatov (Kazakstan); Aktauskaya Gorodskaya Administratsiya, Aktau (Kazakstan); Mangyshlakskij Atomno-Ehnergeticheskij Kombinat, Aktau (Kazakstan); Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Rossijskij Nauchnyj Tsentr 'Kurchatovskij Inst.', Moscow (Russian Federation); Gosudarstvennyj Nauchno-Issledovatel'skij Inst. NPO Luch, Podol'sk (Russian Federation); Yadernoe Obshchestvo, Moscow (Russian Federation); 150 p; Jun 1996; p. 31; Sigma; Kurchatov (Kazakstan); International scientific-practical conference: nuclear power engineering in the Republic of Kazakstan. Perspectives of development (NE-96); Mezhdunarodnaya nauchno-prakticheskaya konferentsiya: yadernaya ehnergetika v Respublike Kazakhstan. Perspektivy razvitiya (YaEh-96); Aktau (Kazakstan); 24-27 Jun 1996
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
BORON COMPOUNDS, CARBIDES, CARBON COMPOUNDS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, IRRADIATION REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS
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Related RecordRelated Record
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AbstractAbstract
[en] Main results of Russian program on decrease of fuel enrichment in testing reactors are presented in the paper with the future perspectives
Original Title
Rossijskaya programma snizheniya obogashcheniya topliva v issledovatel'skuikh reaktorakh
Primary Subject
Record Type
Journal Article
Journal
Voprosy Atomnoj Nauki i Tekhniki. Fizika Radiatsionnykh Povrezhdenij i Radiatsionnoe Materialovedenie; ISSN 0134-5400; ; CODEN VAFMDP; (no.5/88/); p. 3-9
Country of publication
ACTINIDE COMPOUNDS, ACTINIDE NUCLEI, ACTINIDES, ALLOY NUCLEAR FUELS, ALPHA DECAY RADIOISOTOPES, CHALCOGENIDES, EASTERN EUROPE, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, EUROPE, EVEN-ODD NUCLEI, FUELS, HEAVY NUCLEI, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPE ENRICHED MATERIALS, ISOTOPES, MATERIALS, METALS, MINUTES LIVING RADIOISOTOPES, MIXED SPECTRUM REACTORS, NUCLEAR FUELS, NUCLEI, OXIDES, OXYGEN COMPOUNDS, PULSED REACTORS, RADIOISOTOPES, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID FUELS, SOLID HOMOGENEOUS REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, TESTING, URANIUM, URANIUM COMPOUNDS, URANIUM ISOTOPES, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
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