CPR1000延长ILRT周期研究

方兴; 翁文庆; 叶水祥; 张伟; 李剑波

doi:10.13832/j.jnpe.2021.04.0222

CPR1000延长ILRT周期研究

doi: 10.13832/j.jnpe.2021.04.0222

1.
中广核研究院有限公司，广东深圳，518000
2.
苏州热工研究院有限公司，江苏苏州，215000

详细信息

作者简介:
方　兴（1989—），男，工程师，现主要从事核电科研及共性技术改进工作，E-mail: 562120219@qq.com

中图分类号: TL364
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出版历程
- 收稿日期: 2020-06-22
- 修回日期: 2020-07-13
- 刊出日期: 2021-08-15

Study on Extension of Containment ILRT Cycle of CPR1000

1.
China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, 518000, China
2.
Suzhou Nuclear Power Research Institute Co., Ltd., Suzhou, Jiangsu, 215000, China

摘要

摘要: 10 a一次的安全壳整体密封性试验（ILRT）必须占用大修关键路径，时长约100 h。美国94台核电机组已基于安全壳性能评价将ILRT周期延长至15 a。本研究介绍了美国相关安全壳性能评价要求，分析了CPR1000机组延长ILRT周期历史中试验、检查数据的可用性，并以岭澳核电站二期为例计算了延长ILRT周期后的风险，风险增量非常小。结果表明，CPR1000机组基本具备延长ILRT周期的条件。
- 安全壳整体密封性试验（ILRT） /
- 定期试验周期 /
- 安全壳
Abstract: The containment ILRT for 10 years occupies the critical path of refueling for about 100 hours. 94 nuclear power units in the United States have extended the containment ILRT cycle to 15 years based on containment performance evaluation. This paper introduces the performance evaluation requirements of the relevant containment in the United States in detail, and analyzes the extension of the ILRT cycle by the CPR1000 unit, and the availability of historical test data and inspection data. Taking a CPR1000 demonstration unit as an example, the risk after prolonging the safety test of the containment is calculated, and the risk increment is very small. The results show that the CPR1000 unit basically is with the conditions to extend the test period of the containment seal.
- ILRT /
- Periodic test cycle /
- Containment

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表 1 风险接受准则

Table 1. Risk Acceptance Criteria

指标	接受准则
ΔCDF	如果ΔCDF<10⁻⁶，风险增量为：“非常小”，可接受；如果10⁻⁶≤ΔCDF<10⁻⁵，风险增量为“小”，需确保总CDF≤10⁻⁴
ΔLERF	如果ΔLERF<10⁻⁷，风险增量为：“非常小”，可接受；如果10⁻⁷≤ΔLERF<10⁻⁶，风险增量为“小”，需要确保总LERF≤10⁻⁵
集体剂量	集体剂量增量等于0.01人·Sv/a或集体剂量变化率≤1%
ΔCCFP	≤1.5%
CDF—ILRT周期延长后的堆芯损坏频率；ΔCDF—CDF的增量；LERF—ILRT周期延长后的大量早期泄漏频率；ΔLERF—LERF增量；ΔCCFP—ILRT周期延长后的安全壳条件失效概率增量

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表 2 EPRI规定的释放分类及描述

Table 2. Classification and Description of Release Specified by EPRI

安全壳释放类	描述
1	堆芯损坏后初期和长期阶段，安全壳保持完整性。
2	堆芯损坏后，由于安全壳隔离失效而导致的泄漏（即阀门是开着的），此事故类主要指直径大于5.1 cm的安全壳隔离阀关闭失效
3a	堆芯损坏后安全壳完整性因设备隔离失效而破坏，但这些设备不是由B类和C类试验验证的设备，但为小泄漏
3b	堆芯损坏后安全壳完整性因设备隔离失效而破坏，但这些设备不是由B类和C类试验验证的设备，但为大泄漏
4	与局部B类试验相关的密封失效，小泄漏，与ILRT延长无关，不需要进一步研究
5	与局部C类试验相关的密封失效，小泄漏，与ILRT延长无关，不需要进一步研究
6	在堆芯损坏后安全壳完整性因设备卡开在开启位置而关闭失效，通常指维修后的试验，如某一阀门行程试验，卡开失效，但是通常这类失效不会对分析结果有较大的影响，不需要进一步分析
7	严重事故工况或后续的继发失效（超压），如氢爆等
8	安全壳旁通

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表 3 参考核电厂周边80 km处集体剂量风险

Table 3. Population Dose with in 80 km Radius of the Reference Plant

平均比例	集体剂量风险/[人·Sv·（堆·年）⁻¹]	释放类频率/（人·年⁻¹）	集体计量风/（人·Sv）
0.029	1.58×10⁻³	1.23×10⁻⁷	1.28×10⁴
0.019	1.06×10⁻³	1.64×10⁻⁷	6.46×10³
0.002	1.30×10⁻⁴	2.01×10⁻⁸	6.46×10³
0.216	1.20×10⁻²	2.42×10⁻⁶	4.95×10³
0.732	4.06×10⁻²	5.00×10⁻⁶	8.12×10³
0.001	6.00×10⁻⁵	1.42×10⁻⁵	4.23
0.002	1.10×10⁻⁴	1.91×10⁻⁵	5.76
1.0	5.55×10⁻²	4.10×10⁻⁵

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参考文献(14)

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