基于TRACE/FLICA Ⅲ-F程序的国产先进压水堆全失流事故分析研究  

Study on Complete Loss of Flow Accident for Domestic Advanced PWR Based on TRACE/FLICA Ⅲ-F Code

作　　者：贾斌[1] 乔雪冬[1] 高新力[1] 石兴伟[1] 靖剑平[1] 张春明[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《核科学与工程》2017年第2期182-188,共7页Nuclear Science and Engineering

基　　金：国家科技重大专项《CAP1400安全审评关键技术研究》资助项目(No.2013ZX06002001)

摘　　要：国产先进压水堆相比于传统压水堆,系统设备与运行参数均有较大变化,对其开展事故分析研究非常必要。本文首先应用最佳估算系统分析程序TRACE对国产先进压水堆机组进行详细建模,之后根据机组安全分析报告中的分析假设,选取全失流事故进行瞬态分析研究,然后应用FLICA Ⅲ-F程序进行事故瞬态堆芯DNBR分析研究,最终得到的结果可以满足全失流事故验收准则最小DNBR限值1.19的要求。接下来以上研究基础上,选取更加保守的全失流事故分析假设,进一步开展事故分析研究,发现研究结果仍然满足全失流事故验收准则的要求,表明国产先进压水堆机组在全失流事故下安全可靠。Compared with traditional pressurized water reactors, domestic advanced PWR has great changes in system equipment and operation parameters. It is necessary to carry out accident analysis and study for the new reactor. In this paper, firstly the domestic advanced PWR model is established using the best estimation code TRACE in details. Then according to analysis assumptions in the PSAR, the complete loss of flow accident （CLOFA） for domestic advanced PWR is studied, and followed by the study on accident transient core DNBR using FLICA III-F code. It found that the minimumDNBR got from the study can meet the acceptance criteria of 1.19. On this basis, the more conservative analysis further accident analysis and study. It found that all the of the minimum DNBR limit assumptions are chosen for study results can meet the acceptance criteria of CLOFA. It indicates that the domestic advanced PWR is very safe and reliable under CLOFA condition.

关 键 词：TRACE FLICA III—F 全失流 DNBR 

分 类 号：TL331[核科学技术—核技术及应用]