scholarly journals Aging study of boiling water reactor residual heat removal system

1989 ◽  
Author(s):  
R. Lofaro ◽  
M. Subudhi ◽  
W. Gunter ◽  
W. Shier ◽  
R. Fullwood ◽  
...  
Keyword(s):  
Heat Removal ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Aging Study ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Loss of Feed Water Accident in an Integral Pressurized Water Reactor (IPWR)

2010 ◽  
Vol 171-172 ◽  
pp. 379-384
Author(s):  
Khan Salah Ud Din ◽  
Min Jun Peng ◽  
Muhammad Zubair
Keyword(s):  
Heat Removal ◽  
Feed Water ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Heat Removal System ◽  
Water Accident ◽  
Relap5 Code ◽  
Removal System ◽  
Residual Heat

In this paper research has been carried out on Loss of Feed Water Accident (LOFW) scenario of the Integral Pressurized Water Reactor ( IPWR) under two circumstances by the use of thermal hydraulic system code i.e Relap5/Mod3.4. In the first one, Passive Residual Heat Removal System (PRHRS) which is designed to absorb core residual heat in case of transient conditions is included which has the function of operating under the accident vulnerabilities. Concerning with the second case i.e without the use of PRHRS rather a tank of water which has the capacity of about 8% of the total feed water supply and is operated under accident scenario is considered. Taken into account these conditions,first the nodalization diagram of the two cases have been figured out then according to the LOFW accident time event scenario use the Relap5 code to simulate the accident. Finally the graphical explanation (separately) of the two cases with graphical approach as well as the conclusion is given at the end.

Evaluation of a SGTR Accident in the Multi-Application Integrated Pressurized Water Reactor

2010 ◽  
Author(s):  
Liguo Jiang ◽  
Minjun Peng ◽  
Jiange Liu
Keyword(s):  
Steam Generator ◽  
Flow Model ◽  
Heat Removal ◽  
Injection System ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

One of more frequent events in the Pressurized Water Reactor (PWR) is Steam Generator Tube Rupture (SGTR) accident, which is among the main accidents in the field of nuclear safety. This paper studies the SGTR event in the Multi-application Integrated Pressurized Water Reactor (IPWR) using the best-estimate thermal-hydraulic code RELAP5/MOD3.4. In the reactor of IPWR, several Once-Through Steam Generator (OTSG) cassettes are used and located between the core support and the pressure vessel. The tube rupture location is on the top of the tube sheet of a steam generator. Three different tube rupture modeling methods and several different subcooled discharge coefficients in the critical flow model are considered and compared. In the safety analysis, high pressure safety injection system, core makeup system and Passive Residual Heat Removal System (PRHRS) that would affect the accident consequences are considered.

Application of direct passive residual heat removal system to the SMART reactor

2016 ◽  
Vol 89 ◽  
pp. 56-62 ◽  
Author(s):  
Yeon-Sik Kim ◽  
Sung-Won Bae ◽  
Seok Cho ◽  
Kyoung-Ho Kang ◽  
Hyun-Sik Park
Keyword(s):  
Heat Removal ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Experimental study on capability and start-up characteristic of advanced secondary passive residual heat removal system

2021 ◽  
Vol 140 ◽  
pp. 103929
Author(s):  
Qianhua Su ◽  
Haiyan Xu ◽  
Donghua Lu ◽  
Xiaohang Wu ◽  
Xi Yao ◽  
...  
Keyword(s):  
Experimental Study ◽  
Heat Removal ◽  
Start Up ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Analysis of Passive Residual Heat Removal System at Primary Side when Station Blackout Occurs

2014 ◽  
Vol 986-987 ◽  
pp. 231-234
Author(s):  
Jun Teng Liu ◽  
Qi Cai ◽  
Xia Xin Cao
Keyword(s):  
Nuclear Reactor ◽  
Natural Circulation ◽  
Reactor Core ◽  
Saturation Temperature ◽  
Heat Removal ◽  
Primary Circuit ◽  
Station Blackout ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

This paper regarded CNP1000 power plant system as the research object, which is the second-generation half Nuclear Reactor System in our country, and tried to set Westinghouse AP1000 passive residual heat removal system to the primary circuit of CNP1000. Then set up a simulation model based on RELAP5/MOD3.2 program to calculate and analyze the response and operating characteristic of passive residual heat removal system on assumption that Station Blackout occurs. The calculation has the following conclusions: natural circulation was quickly established after accident, which removes core residual heat effectively and keep the core safe. The residual heat can be quickly removed, and during this process the actual temperature was lower than saturation temperature in reactor core.

Sign in / Sign up

Export Citation Format

Share Document