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AbstractAbstract
[en] The fulfillment of the safety analysis acceptance criteria is usually evaluated by separate hot channel calculations using the results of neutronic or/and thermo hydraulic system calculations. In case of an ATWS event (inadvertent withdrawal of control assembly), according to the analysis, a number of fuel rods are experiencing DNB for a longer time and must be regarded as failed. Their number must be determined for a further evaluation of the radiological consequences. In the deterministic approach, the global power history must be multiplied by different hot channel factors (kx) taking into account the radial power peaking factors for each fuel pin. If DNB occurs it is necessary to perform a few number of hot channel calculations to determine the limiting kx leading just to DNB and fuel failure (the conservative DNBR limit is 1.33). Knowing the pin power distribution from the core design calculation, the number of failed fuel pins can be calculated. The above procedure can be performed by conservative assumptions (e.g. conservative input parameters in the hot channel calculations), as well. In case of hot channel uncertainty analysis, the relevant input parameters (k x, mass flow, inlet temperature of the coolant, pin average burnup, initial gap size, selection of power history influencing the gap conductance value) of hot channel calculations and the DNBR limit are varied considering the respective uncertainties. An uncertainty analysis methodology was elaborated combining the response surface method with the one sided tolerance limit method of Wilks. The results of deterministic and uncertainty hot channel calculations are compared regarding to the number of failed fuel rods, max. temperature of the clad surface and max. temperature of the fuel (Authors)
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Vidovszky, Istvan (ed.) (Kiadja az MTA KFKI Atomenergia Kutatointezet, H-1525 Budapest 114, POB 49 (Hungary)); VUJE, Inc., 918 64 Trnava (Slovakia); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, 81219 Bratislava (Slovakia); KFKI Atomic Energy Research Institute, Reactor Analysis Laboratory, H-1525 Budapest 114, POB 49 (Hungary); NPP Dukovany, 675 50 Dukovany (Czech Republic); Institute State Scientific and Technical Center for Nuclear and Radiation Safety, 35-37 Radgospna street, 03142 Kyiv-142 (Ukraine); Kozloduy NPP plc, Kozloduy 3321 (Bulgaria); NPP Bohunice, Jaslovske Bohunice (Slovakia); Nuclear Research Institute Rez plc, CZ-250 68 Husinec-Rez, cp.130 (Czech Republic); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest XI, Mueegyetem rkp. 9, 1111 (Hungary); 753 p; ISBN 963-372-633-4;
; Oct 2006; p. 423-436; 16. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Bratislava (Slovakia); 25-29 Sep 2006; Also available from VUJE, Inc., Okruzna 5, 918 64 Trnava (SK); 9 refs.; 12 figs.; 4 tabs.

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