Analysis of reactor coolant system leak for AP1000 nuclear power plant

Lu LU; Limin ZHENG

doi:10.11889/j.0253-3219.2016.hjs.39.090603

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Analysis of reactor coolant system leak for AP1000 nuclear power plant

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-24

- Analysis of reactor coolant system leak for AP1000 nuclear power plant
- NUCLEAR TECHNIQUES Vol. 39, Issue 9, Article number: 090603(2016)
- 作者机构：
  
  上海核工程研究设计院上海 200233
- 作者简介：
- 基金信息：
  
  Key Design Technology Research of CAP1400
- DOI：10.11889/j.0253-3219.2016.hjs.39.090603
  CLC： TL364
- Received：09 July 2015，
  
  Revised：10 April 2016，
  
  Published：2016-09
- 稿件说明：
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Lu LU, Limin ZHENG. Analysis of reactor coolant system leak for AP1000 nuclear power plant[J]. Nuclear techniques, 2016, 39(9): 090603
DOI：

Lu LU, Limin ZHENG. Analysis of reactor coolant system leak for AP1000 nuclear power plant[J]. Nuclear techniques, 2016, 39(9): 090603 DOI： 10.11889/j.0253-3219.2016.hjs.39.090603.

摘要

第三代AP1000非能动核电厂的主要特征是采用非能动安全原理，使核电厂的系统、设备、构筑物大幅度简化，安全性、可靠性、经济性大幅度提高，以满足美国先进轻水堆业主要求文件的基本要求。本文针对美国业主要求文件（Utility Requirements Document

URD）第三卷第五章《专设安全系统》中对非能动先进轻水堆核电厂反应堆冷却剂系统压力控制功能的要求：在很小的反应堆冷却剂系统（Reactor Coolant System

RCS）净泄漏率（不大于2.27m

·h

-1

）条件下，具有足够的系统冷却剂装量及补水能力，以保证在8h （28800s）内不会触发自动降压系统而进行计算分析，本分析采用安全分析报告小破口失水事故（Loss of coolant accident

LOCA）分析采用的NOTRUMP程序，分析结果表明AP1000核电厂可满足上述美国URD要求。

Abstract

Background

The main design feature of Generation Ⅲ passive power plant is that the passive safety principles are adopted

so the system

equipment and structure are simplified significantly

and the plant safety

reliability and economy are greatly improved.And the utility requirements document(URD)requirements are met by Generation Ⅲ passive power plant.

Purpose

In this paper

a calculation is made to analyze and verify that the requirement in URD volume Ⅲ chapter 5 which is related to the automatic depressurization system(ADS)function is met.The requirement is that sufficient reactor coolant system(RCS)inventory and/or makeup shall be provided so that ADS initiation shall not be required for 8-h following a small leak of reactor coolant system

i.e.

2.27-m

·h

-1

of cold fluid in excess of available charging capacity.

Methods

The small break loss of coolant accident(LOCA)safety analysis code NOTRUMP is used in this calculation.And NOTRUMP is a one dimension

system analysis code.

Results

The results show that the core makeup tanks(CMTs)remain in recirculation phase during the 2.27-m

·h

-1

leak of RCS transient.The water levels in CMTs do not decrease

and the ADS are not actuated accordingly.

Conclusion

The URD requirement described above that ADS initiation shall not be required for 8-h following a small leak of reactor coolant system

i.e.

2.27-m

·h

-1

of cold fluid in excess of available charging capacity is met for AP1000 nuclear power plant.

关键词

Keywords

references

孙汉虹 . 第三代核电技术AP1000 , : 北京中国电力出版社 , 2010 .

Hanhong SUN . Third generation nuclear power technology AP1000 , : Beijing China Electric Power Press , 2010 .

Rodwell E.Assessment of AP1000 conformance with the ALWR URD[R].U.S.Electric Power Research Institute, EPRI-1007741, 2003

Utility requirements document, volume Ⅲ, chapter 5:engineered safety systems(Rev.7)[R].U.S.Nuclear Regulatory Commission, 1995

Chen L.Study on impacts of ADS on AP1000 during SB-LOCA[C].21st International Conference on Nuclear Engineering, ICONE21-15701, Chengdu, China, 2013 http://cn.bing.com/academic/profile?id=1993581532&encoded=0&v=paper_preview&mkt=zh-cn

He S J.The analysis of AP1000 depressurization during small break LOCA[C].21st International Conference on Nuclear Engineering, ICONE21-15968, Chengdu, China, 2013 http://cn.bing.com/academic/profile?id=1980632499&encoded=0&v=paper_preview&mkt=zh-cn

樊普 , 郑尧瑶 . 对NOTRUMP-AP600程序缺少动量通量项的评估与修正 . 原子能科学技术 , 2014 . 48 ( 5 ): 861 - 866 .

Pu FAN , Yaoyao ZHENG . The NOTRUMP-AP600 program the lack of evaluation of momentum flux items with the modified . Atomic Energy Science and Technology , 2014 . 48 ( 5 ): 861 - 866 .

Fittante R L, Gagnon A F.NOTRUMP final validation report for AP600[R].WCAP-14808, USA:Westinghouse Electric Corporation LLC, 1998

R F Wright . Simulated AP1000 response to design basis small-break LOCA events in APEX-1000 test facility . Nuclear Engineering and Technology , 2007 . 39 ( 4 ): 287 - 299 . DOI: 10.5516/NET.2007.39.4.287 http://doi.org/10.5516/NET.2007.39.4.287 .

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