基于衰变热不确定性的压水堆IVR能力边际研究

宋建; 余红星; 邓坚; 向清安; 朱大欢; 许幼幼; 罗跃建

doi:10.13832/j.jnpe.2021.06.0161

基于衰变热不确定性的压水堆IVR能力边际研究

doi: 10.13832/j.jnpe.2021.06.0161

中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213

基金项目: 国家研发计划课题（2019YFB1900703）

详细信息

作者简介:
宋　建(1982—)，男，博士，现主要从事反应堆安全分析研究工作，E-mail: jian_s@hotmail.com

中图分类号: TL331; TL364⁺.4
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- 文章访问数: 203
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- PDF下载量: 19
- 被引次数: 0
出版历程
- 收稿日期: 2020-09-23
- 修回日期: 2020-11-13
- 刊出日期: 2021-12-09

Study on IVR Capability Margin of Pressurized Water Reactor Based on Decay Heat Uncertainty

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 为确定衰变热对高功率压水堆熔融物堆内滞留（IVR）能力边际的影响，采用显著性水平评价与抽样失效率相结合的评价方式，对IVR能力边际进行评价。利用熔融物堆内滞留分析工具CISER开展抽样计算，获得不同核电厂电功率水平、不同衰变热分布参数条件下的下封头壁面热流密度峰值与当地临界热流密度（CHF）的比值，对热流密度比分别开展显著性水平估算与失效率计算，根据小于局部CHF的下封头熔穿准则，判定IVR措施是否有效，以获得IVR能力边际。研究结果表明，若不对下封头内外传热构成进行任何优化措施，电功率超过1400 MW压水堆电厂不推荐单独使用IVR作为严重事故条件缓解措施。
- 衰变热 /
- 临界热流密度（CHF） /
- 熔融物堆内滞留（IVR） /
- 抽样失效率
Abstract: In order to determine the influence of decay heat on the IVR (In-Vessel Retention) capability margin of HPWR, an evaluation method combining significance level evaluation and sampling failure rate was used to evaluate IVR capability margin. Using CISER for IVR to carry out the sampling calculation, the ratio of the peak heat flux on the lower head wall to the local critical heat flux (CHF) under different power levels and decay heat distribution parameters of nuclear power plants was obtained to carry out the significance level estimation and failure rate calculation of the heat flux ratio to judge whether the IVR measure is effective based on the penetration criterion of lower head (less than local CHF) to obtain the IVR capability margin. The results show that IVR alone is not recommended as a serious accident mitigation measure for PWR plants with an electrical power of more than 1400 MW without any optimization of the heat transfer composition inside and outside the lower head.
- Decay heat /
- Critical heat flux (CHF) /
- In-vessel retention (IVR) /
- Sampling failure rate

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图 1 IVR评价路线

Figure 1. IVR Evaluation Route

下载: 全尺寸图片幻灯片

图 2 不同σ_c时的U_α值随额定电功率变化关系

Figure 2. Relationship between U_α and Rated Power under Different σ_c

下载: 全尺寸图片幻灯片

图 3 不同额定电功率时的U_α值随衰变热分布参数的变化关系

Figure 3. Relationship between U_α and Distribution Parameter of Decay Heat under Different Rated Power

下载: 全尺寸图片幻灯片

图 4 额定电功率1600 MW、σ_c=0.5下q/q_CHF统计直方图

Figure 4. Statistical Histogram of q / q_CHFat Rated Power of 1600 MW and σ _c=0.5

下载: 全尺寸图片幻灯片

表 1 IVR熔池参数

Table 1. IVR Melt Pool Parameters

堆芯典型参数	额定电功率水平/MW
堆芯典型参数	1400	1500	1600	1700
锆氧化份额/%	60^[4]
压力容器熔点/℃	1600
压力容器下封头半径/m	2.37^[14]
结构发射率	0.8
不锈钢质量/kg	100000^[14]
金属锆装量/kg	8700
压力容器壁厚/m	0.15^[4]	0.16
UO₂总质量/kg	108000^[14]	115720	123430	131150

下载: 导出CSV

表 2 样本容量n=1500时典型CHF评价模型的成功率

Table 2. Success Rate of Representative CHF Evaluation Model for Sampling Size n=1500

额定电功率/MW	σ_c	典型CHF评价模型
额定电功率/MW	σ_c	UCSB	INEEL	多孔介质涂层	强化绝热层	联合强化模型	界面脱离模型	综合CHF模型
1400	0.4	0.9338	1.0	0.981	0.992	0.993	0.996	0.968
	0.5	0.8932	0.9758	0.953	0.981	0.983	0.985	0.935
	0.6	0.8484	0.9226	0.922	0.96	0.969	0.97	0.906
1500	0.4	0.894	0.9975	0.971	0.988	0.991	0.993	0.954
	0.5	0.876	0.9465	0.939	0.975	0.981	0.981	0.918
	0.6	0.8565	0.909	0.913	0.951	0.958	0.962	0.888
1600	0.4	0.8528	0.9552	0.959	0.985	0.988	0.988	0.938
	0.5	0.8448	0.9408	0.923	0.968	0.974	0.975	0.904
	0.6	0.8384	0.9136	0.898	0.94	0.951	0.953	0.864
1700	0.4	0.8109	0.9146	0.948	0.981	0.985	0.985	0.919
	0.5	0.8245	0.9044	0.914	0.956	0.968	0.969	0.883
	0.6	0.8347	0.8993	0.881	0.929	0.939	0.946	0.835

下载: 导出CSV

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