Scholarlink

Since the National Nuclear Safety Administration of China issued the new version of HAF102 “Safety Code on Nuclear Power Plant Design”, the concept and application of design extension conditions (DEC) have gradually attracted the attention of the nuclear industry and regulatory authorities. However, there is still a blank in the analysis of DEC in passive integrated small pressurized water reactor (ACP100). This paper carried out research on analysis method of design extension conditions without significant fuel degradation (DEC-A), selection method of DEC-A sequences, analysis method of DEC-A safety measures. This paper took ACP1000 as research object, by using probabilistic safety analysis method, combined with engineering judgment and deterministic safety analysis, the list of DEC-A is identified, and the corresponding DEC-A safety measures are put forward to provide guidance for the design of new reactors.

错误：搜索内容不能为空，请输入英文关键词
错误：关键词超出字数限制，请精简
高级检索

Research on Design Extension Conditions Without Significant Fuel Degradation List of Integrated Small Pressurized Nuclear Power Plant

  • 会议论文

  • 发表日期：

    2026年

查看全文
  • Churan Feng,
  • Bin Liu,
  • Guo Chen,
  • Lingzhi Li,
  • Jian Yang,
  • Meiru Liu

摘要

Since the National Nuclear Safety Administration of China issued the new version of HAF102 “Safety Code on Nuclear Power Plant Design”, the concept and application of design extension conditions (DEC) have gradually attracted the attention of the nuclear industry and regulatory authorities. However, there is still a blank in the analysis of DEC in passive integrated small pressurized water reactor (ACP100). This paper carried out research on analysis method of design extension conditions without significant fuel degradation (DEC-A), selection method of DEC-A sequences, analysis method of DEC-A safety measures. This paper took ACP1000 as research object, by using probabilistic safety analysis method, combined with engineering judgment and deterministic safety analysis, the list of DEC-A is identified, and the corresponding DEC-A safety measures are put forward to provide guidance for the design of new reactors.