DMRM在LOCA整体效应实验上的应用

黄涛; 李仲春; 孙微; 邓坚; 丁书华; 刘余; 吴丹; 钱立波; 申亚欧; 杜鹏; 吴增辉

doi:10.13832/j.jnpe.2021.S2.0109

DMRM在LOCA整体效应实验上的应用

doi: 10.13832/j.jnpe.2021.S2.0109

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

详细信息

作者简介:
黄　涛（1989—），男，高级工程师，现从事热工水力与安全分析研究，E-mail: ht_xjtu@163.com

通讯作者:
孙　微， E-mail: sunwei@chinansc.cn

中图分类号: TL364
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- 文章访问数: 95
- HTML全文浏览量: 37
- PDF下载量: 23
- 被引次数: 0
出版历程
- 收稿日期: 2021-07-19
- 录用日期: 2021-12-07
- 修回日期: 2021-11-17
- 刊出日期: 2021-12-29

Application of DMRM on LOCA Integrated Effect Experiment

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

摘要

摘要: 基于中国核动力研究设计院自主研发的确定模型-现实方法（DMRM）的失水事故评价模型，研制了先进反应堆系统分析程序ARSAC。本文将该方法应用于大破口失水事故工况，以验证该方法的正确性及合理性。在验证过程中，首先通过敏感性分析，建立保守的台架系统模型；在此基础上，对包壳峰值温度（PCT）影响较大的输入条件（系统压力、安全注入箱水温等）进行随机抽样，形成计算分析用到的59组工况；利用ARSAC对这些工况进行分析得到最终结果并将最终结果与实验数据进行对比，结果表明，程序计算得到的压力等参数变化与实验数据变化趋势一致，证明了ARSAC计算的正确性；DMRM得到的PCT温度明显高于实验测得值，证明了DMRM的保守性。
- 确定模型-现实方法（DMRM） /
- 先进反应堆系统分析程序（ARSAC） /
- 失水事故 /
- 整体效应实验
Abstract: China Nuclear Power Research and Design Institute independently developed the loss of coolant accident (LOCA) evaluation model of Deterministic Model-Realistic Method (DMRM), and developed the advanced reactor system analysis code ARSAC based on the model. In this paper, this method is applied to large-break LOCA conditions to verify the correctness and rationality of the method. In the verification process, firstly, a conservative bench system model is established through sensitivity analysis; On this basis, the input conditions (system pressure, safety injection tank water temperature, etc.) that have a great impact on the peak cladding temperature (PCT) are randomly sampled to form 59 groups of working conditions for calculation and analysis; These working conditions are analyzed by ARSAC to obtain the final results, and the final results are compared with the experimental data. The results show that the pressure and other parameters calculated by the code are consistent with the experimental data, which proves the correctness of the ARSAC calculation; the PCT temperature obtained by DMRM is significantly higher than the experimental value, which proves the conservativeness of DMRM.
- Deterministic Model-Realistic Method (DMRM) /
- Advanced reactor system analysis code (ARSAC) /
- Loss of coolant accident /
- Overall effect experiment

HTML全文

图 1 不同评价模型的比较

95%/95%——95%的概率能够包络95%的数据

Figure 1. Comparison of Different Evaluation Models

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图 2 59组工况计算得到的PCT

Figure 2. PCT Calculated under 59 Groups of Working Conditions　　　　　　

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图 3 完整环路冷段压力

Figure 3. Pressure of Cold Leg in Intact Loop

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图 4 安注箱压力

Figure 4. Pressure of Safety Injection Tank

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参考文献(3)

[1]	国家核安全局. 核动力厂安全分析用计算机软件开发与应用(试行): 国核安发[2017]323号[A]. 2017-12-20.
[2]	NRC. Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, Appendix K, ECCS evaluation models[S]. US: NRC, 1992.
[3]	BURTT J D. International standard problem 13 (loft experiment L2-5): EGG-NTAP-6276[R]. Idaho National Engineering Liboratory, 1983