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AbstractAbstract
[en] In this study, it is intended to analyse early phases of a protected loss of coolant accident (LOCA) for TR-2 research reactor at Istanbul, and to show applicability of the present model to the other similar types of research reactors. Even though, there has been substantial amount of experimental and numerical works concerning LOCA of research reactor in the literature, most of the works has been done for the latest phase of accident where the core was totally uncovered and being cooled by natural circulation of air. It is our aim to investigate the transient situation since the time when coolant is beginning to be lost throughout one or more of the main coolant pipes which where supposed to be broken guillotine-like to the time when the core is totally uncovered. The modelling of the problem was separated into two phases: in the first phase when the water level of the pool being decreased in a pre-estimated time-dependent way calculated by using modified Bernoulli equation, the conservation equations are solved by a usual implicit finite difference algorithm. The later phase, when water level reaches to the top level of fuel plates and begins to decrease until the bottom of the core, needs some modifications to the approach used for the first phase. Because, the coolants channels among fuel plates are filled with air when the level goes below, and the fuel plates are being cooled by air above the water level. This complexity is resolved using a moving boundary approach in the numerical solution. A Lagrange type interpolation approximation for the derivatives along with interface conditions is the neighborhood of the air-water interface was imported to the numerical algorithm. For the meshes which are not close to the interface above mentioned usual finite difference scheme to solve conservation equations both for air and water side. The analyse is performed for a nominal channel and for a hot channel
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Source
Ministry of Energy and Mineral Resources of the Republic of Kazakhstan, Astana (Kazakhstan); Atomic Energy Committee of the Republic of Kazakhstan, Almaty (Kazakhstan); Inst. of Nuclear Physics, Almaty (Kazakhstan); Nuclear Society of the Republic of Kazakhstan, Almaty (Kazakhstan); Engineering Academy of the Republic of Kazakhstan, Almaty (Kazakhstan); 482 p; ISBN 9185-2-X;
; 2002; p. 29; 2. Eurasian Conference on Nuclear Science and its Application; 2.Eurasian Conference on Nuclear Science and its Application; Almaty (Kazakhstan); 16-19 Oct 2002

Record Type
Book
Literature Type
Conference
Country of publication
ACCIDENTS, CALCULATION METHODS, DIFFERENTIAL EQUATIONS, ENRICHED URANIUM REACTORS, EQUATIONS, IRRADIATION REACTORS, ITERATIVE METHODS, MATERIALS TESTING REACTORS, MATHEMATICAL SOLUTIONS, NUMERICAL SOLUTION, PARTIAL DIFFERENTIAL EQUATIONS, POOL TYPE REACTORS, REACTOR ACCIDENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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