Break frequency calculation of a weld of the reactor outlet pipe of HFETR

Qinglan CUI; Changhong PENG; Yun GUO

doi:10.11889/j.0253-3219.2017.hjs.40.110604

您当前的位置：

首页 >

文章列表页 >

Break frequency calculation of a weld of the reactor outlet pipe of HFETR

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Break frequency calculation of a weld of the reactor outlet pipe of HFETR
- NUCLEAR TECHNIQUES Vol. 40, Issue 11, Article number: 110604(2017)
- 作者机构：
  
  中国科学技术大学核科学技术学院合肥 230026
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2017.hjs.40.110604
  CLC： TL364
- Received：22 May 2017，
  
  Revised：20 July 2017，
  
  Published：10 November 2017
- 稿件说明：
移动端阅览
Qinglan CUI, Changhong PENG, Yun GUO. Break frequency calculation of a weld of the reactor outlet pipe of HFETR[J]. Nuclear techniques, 2017, 40(11): 110604
DOI：

Qinglan CUI, Changhong PENG, Yun GUO. Break frequency calculation of a weld of the reactor outlet pipe of HFETR[J]. Nuclear techniques, 2017, 40(11): 110604 DOI： 10.11889/j.0253-3219.2017.hjs.40.110604.

摘要

近年来，国内外进行多项研究堆概率安全分析，其中管道破口导致的失水事故是堆芯损坏的重要风险来源。本文参考管道破口计算程序PRAISE（Piping Reliability Analysis Including Seismic Events）方法，选取压力壳型研究堆——高通量工程试验堆（High Flux Engineering Test Reactor，HFETR）的运行工况，对其反应堆冷却剂出口管道的焊缝进行分析，得到运行中该处焊缝发生各类破口的频率。

Abstract

Background

In recent years

a number of probabilistic safety analysis for research reactors have been carried out

in which loss-of-coolant accidents due to pipe break are important.

Purpose

The aim is to calculate the break frequency of a weld of the reactor outlet pipe of the high flux engineering test reactor (HFETR).

Methods

This study referred to the algorithm of piping reliability analysis including seismic events (PRAISE) computer code

selected the operating condition of a tank-type research reactor-HFETR.

Results

A weld joint of the reactor coolant outlet pipe was calculated. And the frequencies of all kinds of leaks at the weld joint were obtained.

Conclusion

By doing ultrasonic examination before the operation

the frequency of pipe break can be effectively reduced.

关键词

Keywords

references

International Atomic Energy Agency. Research reactor date base[DB/OL]. 2016-5. https://nucleus.iaea.org/RRDB/RR/ReactorSearch.aspx?filter=0 https://nucleus.iaea.org/RRDB/RR/ReactorSearch.aspx?filter=0

O N Aneziris , C Housiadas , M Stakakis , . Probabilistic safety analysis of a greek research reactor . Annals of Nuclear Energy , 2004 . 31 ( 5 ): 481 - 516 . DOI: 10.1016/j.anucene.2003.09.003 http://doi.org/10.1016/j.anucene.2003.09.003 .

S J Bastin , J Perera . Application of probabilistic safety assessment to parameters of operational limits and conditions of the opal research reactor , : London Engineering Asset Management, Springer , 2006 . 971 - 980 .

Lim E Y. Probability of pipe fracture in the primary coolant loop of a PWR plant Vol.9:PRAISE computer code user's manual[R]. Washington D.C.:U.S. Nuclear Regulatory Commission, 1981

J S You , W F Wu . Probabilistic failure analysis of nuclear piping with empirical study of Taiwan's BWR plants . International Journal of Pressure Vessels and Piping , 2002 . 79 ( 7 ): 483 - 492 . DOI: 10.1016/S0308-0161(02)00061-3 http://doi.org/10.1016/S0308-0161(02)00061-3 .

洪永权 , 卜永熙 . 高通量工程试验堆(HFETR)安全运行十周年 . 核动力工程 , 1990 . 11 ( 6 ): 1 - 5 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG199006000.htm .

Yongquan HONG , Yongxi BU . Ten years safety operation of the high flux engineering test reactor . Nuclear Power Engineering , 1990 . 11 ( 6 ): 1 - 5 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG199006000.htm .

鲍扬民. 高通量工程试验堆本体结构设计[C]. 高通量工程试验堆(HFETR)运行十年论文集, 成都: 四川科学技术出版社, 1990: 39-43.

BAO Yangmin. Reactor body structure design of HFETR[C]. Compilation of literatures on the first ten-year operation of HFETR, Chengdu:Sichuan Science & Technology Press, 1990:39-43

强辉, 吴英华, 卜永熙. HFETR运行限值和运行条件[C]. 高通量工程试验堆(HFETR)运行十年论文集, 成都: 四川科学技术出版社, 1990: 125-130.

QIANG Hui, WU Yinghua, BU Yongxi. The operation limits and conditions for HFETR[C]. Compilation of literatures on the first ten-year operation of HFETR, Chengdu:Sichuan Science & Technology Press, 1990:125-130

GB/T 17395-2008: 无缝钢管尺寸、外形、重量及允许偏差[S]. 2008.

GB/T 17395-2008:Dimensions, shapes, masses and tolerances of seamless steel tubes[S]. 2008

Brust F W, Scott P, Rahman S, et al . Assessment of short through-wall circumferential cracks in pipes[R]. Washington D.C.:U.S. Nuclear Regulatory Commission, 1995

Harris D O, Dedhia D D, Eason E D, et al . Probability of failure in BWR reactor coolant piping[R]. Washington D.C.:U.S. Nuclear Regulatory Commission, 1986

G S Holman . Probability of crack-induced failure in BWR recirculation piping . Nuclear Engineering and Design , 1989 . 113 ( 3 ): 369 - 383 . DOI: 10.1016/0029-5493(89)90029-0 http://doi.org/10.1016/0029-5493(89)90029-0 .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

No data

Related Author

No data

Related Institution

No data

AI问答

Address：2019 Jialuo Road, Jiading, Shanghai, China Postal code：201800
Tel：021-39194977 Email：LHB@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.
Total Visits：881268 Visits Today：795

⁰