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NUCLEAR POWER PLANT EVALUATION SYSTEM AND METHOD

机译:核电站评价系统及方法

摘要

PROBLEM TO BE SOLVED: To respond to the necessity of highly precisely evaluating safety of a plant in a nuclear power plant evaluation system.SOLUTION: A nuclear power plant evaluation system includes: a plant system analysis part 21 which calculates a reactor pressure, a reactor core inlet enthalpy, a reactor core inlet flow rate and a reactor core inlet boron concentration as reactor core boundary conditions for a reactor core consisting of a plurality of fuel rods; a three-dimensional reactor core kinetics analysis part 22 which calculates reactor core output and a reactor core output distribution on the basis of the reactor core boundary conditions; a three-dimensional reactor core heat flow kinetics analysis part 23 which calculates distributions of fuel temperatures, coolant densities and boron concentrations on the basis of the reactor core boundary conditions and the reactor core output distribution; a first correction part 31 which calculates a corrected reactor core output distribution by increasingly correcting an uncertainty at the time of transition for the reactor core output distribution; and a second correction part 32 which calculates a corrected fuel rod output distribution by increasingly correcting an uncertainty at the time of transition for the fuel rod output distribution. The three-dimensional reactor core heat flow kinetics analysis part 23 calculates a minimum DNBR, a fuel center temperature and a cladding tube maximum temperature on the basis of the boundary conditions, the corrected reactor core output distribution and the corrected fuel rod output distribution.SELECTED DRAWING: Figure 2
机译:解决的问题:为了响应在核电厂评估系统中高度精确地评估电厂安全性的必要性。解决方案:核电厂评估系统包括:计算反应堆压力的电厂系统分析部分21,作为由多个燃料棒组成的反应堆堆芯的反应堆堆芯边界条件,堆芯入口焓,反应堆堆芯入口流速和反应堆堆芯入口硼浓度;三维反应堆堆芯动力学分析部分22,其基于反应堆堆芯边界条件计算反应堆堆芯输出和反应堆堆芯输出分布;三维反应堆堆芯热流动力学分析部件23,其基于反应堆堆芯边界条件和反应堆堆芯输出分布来计算燃料温度,冷却剂密度和硼浓度的分布;第一校正部31,通过对电抗器铁心输出分布的转变时的不确定性进行越来越多的校正来计算校正后的电抗器铁心输出分布。第二校正部分32,其通过在过渡时针对燃料棒输出分布的不确定性越来越多地校正来计算校正后的燃料棒输出分布。三维反应堆堆芯热流动力学分析部分23根据边界条件,校正后的反应堆堆芯输出分布和校正后的燃料棒输出分布来计算最小DNBR,燃料中心温度和包壳管最高温度。图2

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