Steady characteristic investigation on passive residual heat removal system of Chinese advanced PWR

Zejun XIAO; Chuan XU; Wenbin ZHUO; Bingde CHEN

doi:10.1016/S1001-8042(08)60023-8

Your Location：

Home >

Browse articles >

Steady characteristic investigation on passive residual heat removal system of Chinese advanced PWR

MISCELLANEOUS | Updated：2021-01-29

- Steady characteristic investigation on passive residual heat removal system of Chinese advanced PWR
- Nuclear Science and Techniques Vol. 19, Issue 1, (2008)
- Affiliations：
  
  1.National Key Laboratory of Bubble Physics & Natural Circulation, Nuclear Power Institute of China, Chengdu 610041, China
- Author bio：
  
  Corresponding author. E-mail address: xzj670711@vip.sina.com
  
  C
  o
  r
  r
  e
  s
  p
  o
  n
  d
  i
  n
  g
  
  a
  u
  t
  h
  o
  r
  .
  
  E
  -
  m
  a
  i
  l
  
  a
  d
  d
  r
  e
  s
  s
  :
  
  x
  z
  j
  6
  7
  0
  7
  1
  1
  @
  v
  i
  p
  .
  s
  i
  n
  a
  .
  c
  o
  m
- Funds：
- DOI：10.1016/S1001-8042(08)60023-8 CLC： TL33
- Published：20 February 2008，
  
  Received：10 October 2007，
Scan for full text
Cite this article
Zejun XIAO, Chuan XU, Wenbin ZHUO, et al. Steady characteristic investigation on passive residual heat removal system of Chinese advanced PWR. [J]. Nuclear Science and Techniques 19(1):58-64(2008)
DOI：

Zejun XIAO, Chuan XU, Wenbin ZHUO, et al. Steady characteristic investigation on passive residual heat removal system of Chinese advanced PWR. [J]. Nuclear Science and Techniques 19(1):58-64(2008) DOI： 10.1016/S1001-8042(08)60023-8.

Steady characteristic investigation on passive residual heat removal system of Chinese advanced PWR 1 corresp first-author Corresponding author. E-mail address: xzj670711@vip.sina.com Corresponding author. E-mail address: xzj670711@vip.sina.com xzj670711@vip.sina.com 1 1 1 National Key Laboratory of Bubble Physics & Natural Circulation, Nuclear Power Institute of China, Chengdu 610041, China National Key Laboratory of Bubble Physics & Natural Circulation, Nuclear Power Institute of China, Chengdu 610041, China Thermal-hydraulic characteristic investigation on passive residual heat removal system (PRHRS) of Chinese advanced PWR was conducted to provide input data for PRHRS design and to demonstrate the feasibility of unique design features. A total of 237 sets of test data at steady state have been obtained and the main influence factors on the two-phase natural circulation flow rate and residual heat removal capability were identified. On the basis of theory analysis, a correlation of two-phase natural circulation was obtained, and relative errors of 95% test data were less than ±16%. There is a considerable effect of the system status parameters on the threshold of height between heat source and heat sink, and its correlation of two-phase natural circulation system has been obtained. The steady characteristic research shows that PRHRS has the capability of removing the core decay power through natural circulation. Chinese advanced PWR Passive residual heat removal system Steady characteristics References Juhn P E , Kupitz J , Cleveland J , et al . Nucl Eng Des , 2000 , 201 : 41 - 59 . Nucl Eng Des Xiao Z J , Zhuo W B , Zheng H , et al . Nucl Eng Des , 2003 , 225 : 305 - 313 . Nucl Eng Des Zvirin Y , Jeuck P R , Sullivan C W , et al . J Heat Transf , 1981 , 103 : 645 - 652 . J Heat Transf Vijayan P K , Mehta S K , Date A W . Int J Heat Mass Transf , 1991 , 34 : 2219 - 223 . Int J Heat Mass Transf Su G H , Jia D N , Fukuda K , et al . Nucl Eng Des , 2002 , 21 : 187 - 198 . Nucl Eng Des Huang Y P , Jia D N . Nucl Sci Eng (in Chinese) , 1997 , 17 : 202 - 207 . Nucl Sci Eng (in Chinese) Ishii M , Kataoka I . Nucl Eng Des , 1984 , 81 : 411 - 425 . Nucl Eng Des Creveling H F , Depaz J F , Baladi J Y , et al . J Fluid Mech , 1975 , 67 : 65 - 84 . J Fluid Mech Reyes J N . IAEA program of technical cooperation , 1995 : 1 - 6 . IAEA program of technical cooperation Chen B D , Xiao Z J , Zhuo W B , et al . J Eng Thermophys (in Chinese) , 1999 , 20 : 17 - 21 . J Eng Thermophys (in Chinese) 10.1016/S1001-8042(08)60023-8 TL33 2007-10-10 2008-02-20 2021-01-19 2008 Nuclear Science and Techniques 01 19

Views

Downloads

CSCD

Alert me when the article has been cited

Submit

Tools

Publicity Resources

The development and verification of thermal-hydraulic code on passive residual heat removal system of Chinese advanced PWR

Steady thermal hydraulic analysis for a molten salt reactor

Survey of experiments and code development for the passive residual heat removal system of PWR in China

Related Author

Ze-Jun XIAO

Sui-Zheng QIU

Wen-Bin ZHUO

Pu FAN

Bing-De CHEN

Dou-Nan JIA

Dalin ZHANG

Suizheng QIU

Related Institution

Xi'an Jiaotong University

State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University

School of Nuclear Science and Technology, Xi'an Jiaotong University

Nuclear Power Institute of China

⁰