AbstractAbstract
[en] Calculated simulation of testing regimes for the ITER reactor first wall model was carried out. Influence on these regimes for the first wall model sizes is studied by calculated way. The rates of heating and transmission regimes of heating are taking into account. The recommendation on selection model size and testing regimes were worked out in the results of the calculation
Original Title
Raschetnoe modelirovanie temperaturnogo polya v modeli pervoj stenki reaktora ITEhR
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1 tab., 10 figs. Issue 1. Atomnaya Ehnergetika i Bezopasnost' AEhS. January 2000
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Journal Article
Journal
Vestnik Natsional'nogo Yadernogo Tsentra Respubliki Kazakhstan; ISSN 1729-7516; ; v. 1(4); p. 54-59
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AbstractAbstract
[en] The possibility of candidate materials test and thermonuclear reactor's elements of blanket is considered. The first wall' materials behaviour and breeding zone under thermal accident are examined. A using of different kinds of heating and its combinations in the IGR reactor could created wide-scale spectrum of TNR' materials tests under accident and transient conditions. 7 refs., 1 tab., 5 figs
Original Title
Modelirovanie povedeniya elementov okhlazhdaemogo litiem blanketa v avarijnykh rezhimakh
Primary Subject
Source
Yadernoe Obshchestvo Respubliki Kazakhstan, Kurchatov (Kazakstan); Natsional'nyj Yadernyj Tsentr, Kurchatov (Kazakstan); Natsional'nyj Yadernyj Tsentr, Kurchatov (Kazakstan). Inst. Atomnoj Ehnergii; 144 p; 1995; p. 128-132; 20 years of energy start-up of IVG-1 reactor; 20 let ehnergeticheskogo puska reaktora IVG-1; Kurchatov (Kazakstan); 26-28 Apr 1995
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Chekhonadskikh, A.M.; Vurim, A.D.; Vasilyev, Yu.S.; Pivovarov, O.S.; Shestakov, V.P.; Tazhibayeva, I.L.
Proceedings of the third IEA international workshop on beryllium technology for fusion1998
Proceedings of the third IEA international workshop on beryllium technology for fusion1998
AbstractAbstract
[en] In this report program on investigations of beryllium emissivity and transient processes on overheated beryllium surface attacked by water steam to be carried out in IAE NNC RK within Task S81 TT 2096-07-16 FR. The experimental facility design is elaborated in this Report. (author)
Primary Subject
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Kawamura, Hiroshi; Okamoto, Makoto (eds.); Japan Atomic Energy Research Inst., Tokyo (Japan); 375 p; Jan 1998; p. 69-73; 3. IEA international workshop on beryllium technology for fusion; Mito, Ibaraki (Japan); 22-24 Oct 1997
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Report
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Conference
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ALKALINE EARTH METALS, CHEMICAL REACTIONS, CLOSED PLASMA DEVICES, ELEMENTS, EXPERIMENTAL REACTORS, FLUIDS, GASES, MATERIALS, METALS, OPTICAL PROPERTIES, PHYSICAL PROPERTIES, REACTORS, RESEARCH AND TEST REACTORS, SIMULATION, STRUCTURAL MODELS, SURFACE PROPERTIES, TEMPERATURE RANGE, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTORS, TOKAMAK DEVICES, TOKAMAK TYPE REACTORS, VAPORS
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Shestakov, V.P.; Andriyash, A.V.; Nogin, V.N.; Chekhonadskikh, A.M.
Abstracts of reports of the international scientific-practical conference1996
Abstracts of reports of the international scientific-practical conference1996
AbstractAbstract
[en] Short communication
Original Title
Analiz vozmozhnosti ehksperimental'nogo modelirovaniya v reaktore IGR sryva plazmy na devertore termoyadernogo reaktora
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Secondary Subject
Source
Koltysheva, G.I.; Perepelkin, I.G. (eds.). Funding organisation: 7042021KZ; 7041869KZ; 7042022KZ; 7041851KZ; 7042024KZ; 7042025KZ; 7041949KZ; 7042026KZ; 7042027KZ; 7042028KZ; 4205370RU; 7041774RU; 7042029RU; 7041736RU; 150 p; Jun 1996; p. 114; Sigma; Kurchatov (Kazakstan); International scientific-practical conference: nuclear power engineering in the Republic of Kazakstan. Perspectives of development (NE-96); Yadernaya ehnergetika v Respublike Kazakhstan. Perspektivy razvitiya; Aktau (Kazakstan); 24-27 Jun 1996
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AbstractAbstract
[en] The report presents results of beryllium emissivity factor measurements within 700-1300 K temperature range. The tests were conducted at Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakhstan to receive experimental data for verification of calculation programs describing an accident involving water coolant discharge into ITER reactor vacuum cavity. (author)
Original Title
Ehksperimenty po izucheniyu vzaimodejstviya berilliya s parom, opredelenie stepeni chernoty okislennogo berilliya
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Source
5 figs. Issue 1. Atomnaya Ehnergetika i Bezopasnost' AEhS. March 2001
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Journal Article
Journal
Vestnik Natsional'nogo Yadernogo Tsentra Respubliki Kazakhstan; ISSN 1729-7516; ; v. 1(4); p. 19-23
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ACCIDENTS, ALKALINE EARTH METALS, CHEMICAL REACTIONS, CLOSED PLASMA DEVICES, ELEMENTS, MATERIALS, METALS, OPTICAL PROPERTIES, PHYSICAL PROPERTIES, SURFACE PROPERTIES, TEMPERATURE RANGE, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTOR WALLS, THERMONUCLEAR REACTORS, TOKAMAK DEVICES, TOKAMAK TYPE REACTORS
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AbstractAbstract
[en] Purpose of the work is obtaining of precision description of heat propagation due to reaction evolving in the and it interaction on the ITER structures and atmosphere within reactor vessel and prediction of hydrogen release in the case of the beryllium with vapour reaction. For the experiments conducting the unit for interaction of vapour and metal is implemented. The unit consists of vacuum chamber in which are arrangement ed the following systems: System for vacuuming; system for preparation and water vapour feed back into the chamber; System for measurement and registration of parameters. Quantity of hydrogen have being measured by volume method. Hydrogen substituted water out of gas bell and its volume is determined by pressure under the bell with taking into account the water vapour partial pressure and hydrogen solubility in the water
Original Title
Ustanovka dlya issledovaniya vzaimodejstviya berilliya s vodyanym parom
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4 tabs., 2 figs. Issue 1. Atomnaya Ehnergetika i Bezopasnost' AEhS. January 2000
Record Type
Journal Article
Journal
Vestnik Natsional'nogo Yadernogo Tsentra Respubliki Kazakhstan; ISSN 1729-7516; ; v. 1(4); p. 42-45
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Kolbasov, B.N.; Topilskij, L.N.; Vurim, A.D.; Chekhonadskikh, A.M.; Ishanov, E. O.; Shestakov, V.P.
Nuclear power technologies. Abstracts of reports2000
Nuclear power technologies. Abstracts of reports2000
AbstractAbstract
[en] This report includes results of measuring beryllium emissivity factor in wide temperature range. Experiments were made at IAE NNC RK in order to obtain experimental data meant for verification of calculation codes describing accident situation involving water coolant release into vacuum cavity of ITER reactor. The outcomes, obtained from the experiments conducted under different conditions, have various quantitative values. But, depending on the basic determinative values, they obey to common laws. When the partial pressure of water steam in the vacuum chamber increases, beryllium samples are oxidized more intensively. However, a tendency to emissivity factor variations remains the same, not depending on a water steam concentration value
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. 63-64; International seminar on nuclear power technologies; Mezhdunarodnyj seminar po tekhnologii yadernoj ehnergetiki; Astana (Kazakhstan); 14-17 May 2000
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