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Aden, V.G.; Kartashov, E.F.; Lukichev, V.A.
Proceedings of the 1994 international meeting on reduced enrichment for research and test reactors1997
Proceedings of the 1994 international meeting on reduced enrichment for research and test reactors1997
AbstractAbstract
[en] During the last year after the 16-th International Conference on Reducing Fuel Enrichment in Research Reactors held in October, 1993 in Oarai, Japan, the conclusive stage of the Program on reducing fuel enrichment (to 20% in U-235) in research reactors was finally made up in Russia. The Program was started late in 70th and the first stage of the Program was completed by 1986 which allowed to reduce fuel enrichment from 80-90% to 36%. The completion of the Program current stage, which is counted for 5-6 years, will exclude the use of the fuel enriched by more than 20% from RF to other countries such as: Poland, Czeck Republick, Hungary, Roumania, Bulgaria, Libya, Viet-Nam, North Korea, Egypt, Latvia, Ukraine, Uzbekistan and Kazakhstan. In 1994 the Program, approved by RF Minatom authorities, has received the status of an inter-branch program since it was admitted by the RF Ministry for Science and Technical Policy. The Head of RF Minatom central administrative division N.I.Ermakov was nominated as the Head of the Russian Program, V.G.Aden, RDIPE Deputy Director, was nominated as the scientific leader. The Program was submitted to the Commission for Scientific, Technical and Economical Cooperation between USA and Russia headed by Vice-President A. Gore and Prime Minister V. Chemomyrdin and was given support also
Primary Subject
Source
Argonne National Lab., IL (United States); 427 p; Aug 1997; p. 27-31; International meeting on reduced enrichment for research and test reactors; Williamsburg, VA (United States); 18-22 Sep 1994; ALSO AVAILABLE FROM OSTI AS DE98000036; NTIS; INIS; US GOVT. PRINTING OFFICE DEP
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Radaev, A.I.; Sokolov, S.A.; Kravtsova, O.A.; Lukichev, V.A.
Seminar Neutronika-2012. Neutron-physical problems of nuclear-power engineering. Program and abstracts2012
Seminar Neutronika-2012. Neutron-physical problems of nuclear-power engineering. Program and abstracts2012
AbstractAbstract
No abstract available
Original Title
Issledovanie konversii issledovatel'skogo reaktora MARIYa na nizkoobogashchennoe uranovoe toplivo
Primary Subject
Source
Goskorporatsiya Rosatom, Moscow (Russian Federation); GNTs RF - Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation); 81 p; 2012; p. 61; Seminar Neutronika-2012. Neutron-physical problems of nuclear-power engineering; Seminar Nejtronika-2012. Nejtronno-fizicheskie problemy atomnoj ehnergetiki; Obninsk (Russian Federation); 30 Oct - 2 Nov 2012
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ACTINIDES, BERYLLIUM MODERATED REACTORS, ELEMENTS, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HYDRAULICS, IRRADIATION REACTORS, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, MATERIALS, MECHANICS, METAL MODERATED REACTORS, METALS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, THERMAL REACTORS, URANIUM, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Aden, V.G.; Kartashev, E.F.; Lukichev, V.A.
12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies. Book of abstracts2001
12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies. Book of abstracts2001
AbstractAbstract
No abstract available
Original Title
Rossijskaya programma snizheniya obogashcheniya topliva v issledovatel'skikh reaktorakh kak odin iz faktorov nerasprostraneniya yadernogo oruzhiya
Primary Subject
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Yadernoe Obshchestvo Rossii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 104 p; ISBN 5-85165-655-7; ; 2001; p. 90, 91; 12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies; 12. Ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Issledovatel'skie reaktory: nauka i vysokie tekhnologii; Dimitrovgrad (Russian Federation); 25-29 Jun 2001
Record Type
Book
Literature Type
Conference
Country of publication
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Kuatbekov, R.P.; Lukichev, V.A.; Osipovich, S.V.; Sokolov, S.A.; Tret'yakov, I.T.; Trushkin, V.I.
13. Russian meeting Safety of research nuclear plants. Book of abstracts2011
13. Russian meeting Safety of research nuclear plants. Book of abstracts2011
AbstractAbstract
No abstract available
Original Title
Issledovatel'skij reaktor dlya tsentrov yadernykh issledovanij
Primary Subject
Source
Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii Rosatom, Moscow (Russian Federation); Otkrytoe Aktsionernoe Obshchestvo Gosudarstvennyj Nauchnyj Tsentr - Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); Tsentr Sbora i Analiza Informatsii po Bezopasnosti Issledovatel'skikh Yadernykh Ustanovok, Dimitrovgrad (Russian Federation); 62 p; ISBN 978-5-94831-111-1; ; 2011; p. 30-32; 13. Russian meeting Safety of research nuclear plants; 13. Rossijskoe soveshchanie Bezopasnost' issledovatel'skikh yadernykh ustanovok; Dimitrovgrad (Russian Federation); 23-27 May 2011; 1 tab.
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Book
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AbstractAbstract
[en] The main results of work performed as part of a program to decrease the enrichment of fuel in research reactors and prospects for the future are present. The goals, the main stages of the program, and the degree to which they have been completed are described. The results of laboratory, design, technological work, and reactor and post-reactors tests on new fuel elements and fuel assemblies are presented. It is shown that the existing scientific and technological results are the basis for performing development work on a new generation of fuel elements for existing and future designs of research reactors
[ru]
Представлены основные результаты работ по программе снижения обогащения топлива в исследовательских реакторах и перспективы на будущее. Охарактеризованы цели, основные этапы программы и степень их завершенности. Приведены результаты лабораторных, конструкторских и технологических разработок, реакторных и послереакторных испытаний новых твэлов и ТВС. Показано, что имеющиеся уже сейчас научные и технологические результаты являются основой для выполнения ОКР по созданию твэла нового поколения для существующих и будущих проектов исследовательских реакторовOriginal Title
Snizhenie obogashcheniya topliva v issledovatel'skikh reaktorakh
Primary Subject
Source
4 refs., 5 figs.
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Aden, V.G.; Artamkin, V.N.; Kartashov, E.F.; Lukichev, V.A.; Arkhangelsky, N.V.
Proceedings of the 16th international meeting on reduced enrichment for research and test reactors1994
Proceedings of the 16th international meeting on reduced enrichment for research and test reactors1994
AbstractAbstract
[en] The results of in-pile tests of fuel assemblies with 36% enrichment are presented. The report contents the information about the results of fuel assembly IVV-2M type in-pile tests for the safe operation limits discovering in power ramp and loss of flow operation regimes. (author)
Primary Subject
Source
Japan Atomic Energy Research Inst., Tokyo (Japan); 466 p; Mar 1994; p. 183-190; 16. international meeting on reduced enrichment for research and test reactors; Oarai, Ibaraki (Japan); 4-7 Oct 1993
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACTINIDE COMPOUNDS, ACTINIDES, ALLOYS, CHALCOGENIDES, DIMENSIONS, ELEMENTS, ENRICHED URANIUM, ISOTOPE ENRICHED MATERIALS, MATERIALS, METALS, OXIDES, OXYGEN COMPOUNDS, REACTORS, RESEARCH AND TEST REACTORS, TESTING, URANIUM, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Arkhangelsky, N.V.; Aden, V.G.; Artamkin, V.N.; Bovin, A.P.; Kartashev, E.F.; Lukichev, V.A.; Stetsky, Y.A.
Proceedings of the 16th international meeting on reduced enrichment for research and test reactors1994
Proceedings of the 16th international meeting on reduced enrichment for research and test reactors1994
AbstractAbstract
[en] This report describes research reactors in Russia and built abroad on Russian projects, and main features of the Russian programme of reducing fuel enrichment in research reactors. (author)
Primary Subject
Source
Japan Atomic Energy Research Inst., Tokyo (Japan); 466 p; Mar 1994; p. 43-49; 16. international meeting on reduced enrichment for research and test reactors; Oarai, Ibaraki (Japan); 4-7 Oct 1993
Record Type
Report
Literature Type
Conference
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Aden, V.G.; Gabaraev, B.A.; Kartashov, E.F.; Lukichev, V.A.
Abstracts and papers of the 1997 International RERTR Meeting1997
Abstracts and papers of the 1997 International RERTR Meeting1997
AbstractAbstract
[en] The report presents the main results of works under the Russian RERTR Program carried out in the last year and plans for 1998. Works under the Russian RERTR Program proceeded during the last year after the 19th International Meeting on RERTR held in Seoul. It is known that the Russian Program stipulates three principle stages of the works. Stage 1 includes development of fuel elements and fuel assemblies of VVR-M2, IRT and MR types with higher density fuel uranium dioxide. Stage 2 is concerned with development of high-density fuel (U3Si2, U3Si, U6Fe, UZr and others). Stage 3 involves development of fuel elements and fuel assemblies of VVR-MS IRT and IVV-10 types with high-density fuel. (author)
Primary Subject
Source
Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States); 259 p; Oct 1997; [5 p.]; 20. international meeting on Reduced Enrichment for Research and Test Reactors (RERTR); Jackson Hole, WY (United States); 5-10 Oct 1997; Also available online: http://www.td.anl.gov/Programs/RERTR/PAPERS97.html; 2 figs
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACTINIDE COMPOUNDS, ACTINIDES, CHALCOGENIDES, ELEMENTS, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, MATERIALS, MATERIALS TESTING REACTORS, METALS, OXIDES, OXYGEN COMPOUNDS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SILICIDES, SILICON COMPOUNDS, TANK TYPE REACTORS, THERMAL REACTORS, TRANSITION ELEMENT COMPOUNDS, URANIUM, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWR TYPE REACTORS
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Golosov, O.A.; Semerikov, V.B.; Teplykh, A.E.; Lyutikova, M.S.; Kartashev, E.F.; Lukichev, V.A.
European Nuclear Society, Brussels (Belgium)
International topical meeting. Research Reactor Fuel Management (RRFM) and meeting of the International Group on Reactor Research (IGORR)2007
European Nuclear Society, Brussels (Belgium)
International topical meeting. Research Reactor Fuel Management (RRFM) and meeting of the International Group on Reactor Research (IGORR)2007
AbstractAbstract
[en] The data about the phase and structural state of (U,Mo)Alx layer have been scarce so far, thereby precluding from development of the measures for reducing the rate of layer growing. This paper presents the results of the structure study on the dispersed uranium-molybdenum fuel after irradiation to different burn up levels from 33 to 97% and one-hour annealings within temperatures of 150 to 580 Celsius degrees by the neutron diffraction method. The following conclusions have been drawn, -) the percentage of γ-U-9%Mo phase depends only slightly on burnup; -) the percentage of UAl3 crystal phase does not exceed 0.5% and is almost constant in the range of burnups from 33% to 97%; -) the percentage of the Mo90U10 phase is constant and equals to about 1.5% and hardly depends on burnup; -) the percentage of amorphous phase such as (U,Mo)Alx depends on irradiation parameters and increases as fuel burnup rises; -) annealing in temperatures above 300-350 C degrees results in crystallization of the amorphous phase with formation of the UAl3 intermetallic phase
Primary Subject
Source
European Nuclear Society, Brussels (Belgium); 492 p; 2007; p. 478-482; 11. International topical meeting. Research Reactor Fuel Management (RRFM) and meeting of the International Group on Reactor Research (IGORR); Lyon (France); 11-15 Mar 2007; 4 refs.
Record Type
Miscellaneous
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Conference
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Aden, V.G.; Lukichev, V.A.; Kartashev, E.F.; Gibadullin, R.Kh.; Popov, V.V.; Troyanov, V.M.
VII Russian conference on reactor material science. Abstracts2003
VII Russian conference on reactor material science. Abstracts2003
AbstractAbstract
No abstract available
Original Title
Tekhnologicheskie issledovaniya po primeneniyu uran-molibdenovogo topliva dlya issledovatel'skikh reaktorov s ponizhennym obogashcheniem urana
Primary Subject
Secondary Subject
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Federal'noe Gosudarstvennoe Unitarnoe Predpriyatie Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Nauchno-Issledovatel'skij Institut Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 424 p; ISBN 5-94831-020-5; ; 2003; p. 382-383, 384-385; 7. Russian conference on reactor material science; VII Rossijskaya konferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 2003
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Book
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