原子能科学技术2012，Vol.46Issue(1)：37-42,6.
先进压水堆熔融物堆内滞留参数不确定分析研究
Research on Uncertainty Analysis of In-Vessel Retention Parameters in Advanced PWR
徐红 1周志伟2
作者信息
- 1. 国家核电技术研发中心,北京100190
- 2. 清华大学核能与新能源技术研究院,北京100084
- 折叠
摘要
Abstract
A molten pool comes into being after core damage under severe accident conditions in PWR plant. It has many uncertainty factors about the forming process of the molten pool, and this will affect the validity of in-vessel retention (IVR) strategy of reactor vessel. Based on the two-layer IVR model of AP1000, the study on the parameters uncertainty of molten pool under assumed severe accident conditions for external reactor vessel cooling (ERVC) was achieved, including sensitivity analysis and Latin hypercube sampling (LHS) probability analysis of the parameters. The results show that decay power has the essential effect on IVR evaluation parameters. Actions such as water injection from upper plenum should be taken to delay the core molten time. The mass of stainless steel in debris has great impact on parameters of molten metal layer. Some penalty materials could be placed in vessel to mitigate the heat focus effect of the metal layer. The invalidation probability of vessel outside of molten ceramic layer is merely 1.2%, but the invalidation probability of vessel outside of molten metal layer reaches up to 20%, This study has certain directive significance on future IVR strategy research and design, and also provides theoretical support to safety evaluation of PWR plants.关键词
严重事故/堆内滞留/敏感性分析/不确定分析/拉丁超立方抽样Key words
severe accident/in-vessel retention/sensitivity analysis/uncertainty analysis/Latin hypercube sampling分类
能源科技引用本文复制引用
徐红,周志伟..先进压水堆熔融物堆内滞留参数不确定分析研究[J].原子能科学技术,2012,46(1):37-42,6.
