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作 者:齐少璞 杨红义[1] 杨晓燕[1] 王晓坤[1] 王晋[1] 叶尚尚[1] QI Shaopu;YANG Hongyi;YANG Xiaoyan;WANG Xiaokun;WANG Jin;YE Shangshang(Division of Reactor Engineering Technology Research,China Institute of Atomic Energy,Beijing 102413,China)
出 处:《原子能科学技术》2020年第2期273-280,共8页Atomic Energy Science and Technology
摘 要:系统分析程序是开展反应堆安全分析的重要工具之一,也可用于开展系统瞬态实验过程的分析。法国凤凰堆(Phenix)在停运之前开展的自然循环实验是钠冷快堆领域非常重要的系统瞬态实验,为研究钠冷快堆的瞬态特点提供了很好的参考。为分析此实验过程,利用自主研发的系统分析程序FR-Sdaso对凤凰堆进行建模,对其自然循环实验开展计算分析,并将主要参数的计算值与实验值进行了对比分析。结果表明,FR-Sdaso可较好地模拟此实验的瞬态过程,可用于开展钠冷快堆此类瞬态的安全分析。System analysis code is one of the most important tools for reactor safety analysis, and can also be used to simulate the system transient test. The natural circulation test performed during the French Phenix end-of-life test, which provides a very reliable benchmark for sodium-cooled fast reactor(SFR) system transient behavior research, is very valuable for SFR. In order to analyze this test, the Phenix was modeled with the self-developed system analysis code FR-Sdaso, and the natural circulation test was calculated by the code. The calculation results were compared with the test data. The results show that the overall response of the reactor is predicted reasonably well by FR-Sdaso and FR-Sdaso can be used for this kind of SFR safety analysis.
关 键 词:钠冷快堆 系统分析程序 FR-Sdaso Phenix自然循环实验
分 类 号:TL425[核科学技术—核技术及应用]
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