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首页> 美国政府科技报告 >Calculation with the CATHARE code of the SBL-22 PACTEL experiment with a new input data deck of the main circulation pump (0-D pump model)
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Calculation with the CATHARE code of the SBL-22 PACTEL experiment with a new input data deck of the main circulation pump (0-D pump model)

机译：使用sBL-22 paCTEL实验的CaTHaRE代码计算主循环泵的新输入数据板（0-D泵型号）

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In order to improve safety in nuclear power plants, research programs have been launched to study the physical phenomena during various transients and accident scenarios. Several thermal hydraulic computer codes have been developed to simulate these behaviors. Among them is CATHARE, a French thermal hydraulic code by EDF, Framatome and CEA, for the best estimate simulation of PWR loss of coolant accidents. The assessment of all these codes, used for safety analysis of nuclear reactors is based on experimental results achieved with test facilities and transients in commercial power plants. With particular attention to the VVER reactors used in Finland, PACTEL facility (PArallel Channel TEst Loop) was designed to simulate thermal hydraulic phenomena. In the past calculations with CATHARE code were always performed with the LOBIpump 0-D model which does not reflect the actual experimental setup in PACTEL facility. In order to determine possible consequences on the results of thermal hydraulic behavior two test calculations were performed with CATHARE 2 V1.3U(sub 1) code. Main focus of this work was to implement and verify the performance of new data for the 0-D pump model in the input data deck for PACTEL facility. These results were compared to a calculation using the already existing data for LOBI-pump. The experiment chosen is the small break loss of coolant SBL-22 with the large diameter steam generators. In this case experimental results are well understood, pump performance relevant data are measured and an input data deck is already existing. (authors) (16 refs., 55 figs., 3 tabs.). (Atomindex citation 27:068631)

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