本文選題：LBLOCA + 最佳估算及不確定性分析　； 參考：《原子能科學技術》2017年07期

【摘要】：我國某大功率非能動壓水堆首次采用標準設計的方法。本文基于TRACE程序,采用最佳估算及不確定性分析方法對該電廠大破口失水事故開展了獨立審核計算,并探討了該方法在核安全審評中的應用。最佳估算結果表明,該壓水堆大破口失水事故下包殼峰值溫度低于驗收準則限值。該計算結果可作為獨立審核計算的重要部分應用于核電廠安全審評中。
[Abstract]:The standard design method is used for the first time in a high power passive pressurized water reactor (PWR) in China. In this paper, based on trace program, the method of optimal estimation and uncertainty analysis is used to carry out the independent audit and calculation of the water loss accident in the large break of the power plant, and the application of this method in the nuclear safety evaluation is discussed. The results show that the peak temperature of the cladding is lower than the limit of acceptance criterion. The calculated results can be used as an important part of the independent audit calculation in the safety evaluation of nuclear power plants.
【作者單位】： 環(huán)境保護部核與輻射安全中心;
【基金】：國家科技重大專項資助項目(2013ZX06002001-006,2015ZX06004001001-002)
【分類號】：TL364
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本文編號：2089199