Transient calculation of natural circulation for pool-type research reactor

Dai Tao; Huang Hongwen; Ma Jimin

doi:10.11884/HPLPB201830.180009

Volume 30 Issue 8

Aug. 2018

Turn off MathJax

Article Contents

Article Navigation > High Power Laser and Particle Beams > 2018 > 30(8): 086001

Dai Tao, Huang Hongwen, Ma Jimin. Transient calculation of natural circulation for pool-type research reactor[J]. High Power Laser and Particle Beams, 2018, 30: 086001. doi: 10.11884/HPLPB201830.180009

Citation:

Dai Tao, Huang Hongwen, Ma Jimin. Transient calculation of natural circulation for pool-type research reactor[J]. High Power Laser and Particle Beams, 2018, 30: 086001. doi: 10.11884/HPLPB201830.180009

Citation:

PDF( 2835 KB)

Transient calculation of natural circulation for pool-type research reactor

doi: 10.11884/HPLPB201830.180009

Institute of Nuclear Physics and Chemistry, CAEP, P.O.Box 919-226, Mianyang 621900, China

Received Date: 2018-01-08
Rev Recd Date: 2018-04-04
Publish Date: 2018-08-15

Abstract

Abstract

The natural circulation capacity is an important parameter that characterizes the safety capability of a nuclear reactor.We calculated the transient characteristics under the conditions with and without emergency cooling system by RELAP5/Mod 3.4, analyzed the transient natural circulation capability of the coolant flow direction reversal process, and acquired the maximum transient transfer capability.The results show: the emergency cooling system reduced fuel and coolant temperatures significantly and improved the safety of the reactor; when the decay power was reduced to 590 kW, the auxiliary pump was turned off and the reactor could be brought into a safe state with natural circulation.
- pool-type research reactor,
- natural circulation capability,
- RELAP5,
- flow reversal,
- transient calculation

FullText(HTML)

References(8)

References

[1]	杨祖毛, 王飞, 王文康, 等. 闭合回路单相自然循环稳态特性研究[J]. 核动力工程, 1999, 20: 248-253. https://www.cnki.com.cn/Article/CJFDTOTAL-HDLG903.006.htm Yang Zumao, Wang Fei, Wang Wenkang, et al. Investigation on steady-state performance of single-phase natural circulation for enclosed loop. Nuclear Power Engineering, 1999, 20: 248-253 https://www.cnki.com.cn/Article/CJFDTOTAL-HDLG903.006.htm
[2]	黄彦平. 压水反应堆自然循环特性研究[D]. 西安: 西安交通大学, 2003: 21-30. Huang Yanping. Study on natural circulation characteristics of a pressurized water reactor. Xi'an: Xi'an Jiaotong University, 2003: 21-30
[3]	田文喜, 秋穗正, 王甲强, 等. 中国先进研究堆稳态自然循环能力分析[J]. 核动力工程, 2007, 28(2): 13-18. https://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200702003.htm Tian Wenxi, Qiu Suizheng, Wang Jiaqiang, et al. Study on steady natural circulation capacity of CARR. Nuclear Power Engineering, 2007, 28(2): 13-18 https://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200702003.htm
[4]	黄洪文, 刘汉刚, 杨晓斌, 等. 池式研究堆自然循环能力试验及数值模拟[J]. 原子能科学技术, 2012, 46(s1): 206-210. https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2012S1045.htm Huang Hongwen, Liu Hangang, Yang Xiaobin, et al. Natural circulation capacity experiment and numerical simulation for pool-type research reactor. Atomic Energy Science and Technology, 2012, 46(s1): 206-210 https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2012S1045.htm
[5]	Kaminaga M, Ikawa H. COOLOD-N: A computer code for the analysis of steady-state thermal-hydraulics in plate type research reactor[J]. JAERI-M, 1990, 90(21): 2201-2213.
[6]	Nuclear Safety Analysis Division. RELAP5/MOD 3.3 code manual volume I: Code structures, system models, and solution methods[M]. Washington, D.C. : United States Nuclear Regulatory Commission, 2001.
[7]	EJ/T 745-2001, 轻水堆核燃料衰变热功率的计算[S]. EJ/T 745-2001, Calculation of decay heat power in the nuclear fuel of light water reactors
[8]	Sudo Y, Ando H, Ikawa H, et al. Core thermal hydraulic design with 20% LEU fuel for upgraded research reactor JRR-3[J]. Journal of Nuclear Sci & Tech, 1985, 22(7): 551-564.