Advanced search
Publication Cover
Nuclear Technology Volume 103, 1993 - Issue 3
Submit an article Journal homepage
8
Views
7
CrossRef citations to date
0
Altmetric
Technical Paper

Simulation of Loss of RHR During Midloop Operations and the Role of Steam Generators in Decay Heat Removal Using the RELAP5/MOD3 Code

Yassin A. HassanTexas A&M University, Department of Nuclear Engineering College Station, Texas 77843-3133
&
Laxminarayan L. RajaTexas A&M University, Department of Nuclear Engineering College Station, Texas 77843-3133
Pages 310-319 | Published online: 10 May 2017

Citations (7)

Keep up to date with the latest research on this topic with citation updates for this article.

Subscribe to citation updates

Read on this site (7)

Kwang Won Seul, Young Seok Bang & Hho Jung Kim. (2000) Mitigation Measures Following a Loss-of-Residual-Heat-Removal Event during Shutdown. Nuclear Technology 132:1, pages 152-166.
Read now
Kwang Won Seul, Young Seok Bang & Hho Jung Kim. (1999) Plant Behavior Following a Loss-of-Residual-Heat-Removal Event Under a Shutdown Condition. Nuclear Technology 126:3, pages 265-278.
Read now
J. A. Mowrey, P. R. Boylan & S. I. Abdel-Khalik. (1998) Modeling of Boiling Water Reactor Feedwater Control Algorithms. Nuclear Technology 124:3, pages 223-242.
Read now
Yuh-Ming Ferng & Shau-Shei Ma. (1996) Investigation of System Responses of the Maanshan Nuclear Power Plant to the Loss of Residual Heat Removal During Midloop Operation Using a RELAP5/MOD3 Simulation. Nuclear Technology 116:2, pages 160-172.
Read now
Yuh-Ming Ferng & Chien-Hsiung Lee. (1996) Assessment of the Simulation Capability of RELAP5/MOD3 Compared with IIST Tests for Loss of the Residual Heat Removal System During Midloop Operation. Nuclear Technology 116:1, pages 19-33.
Read now
J. A. Mowrey, S. I. Abdel-Khalik & K. W. Ross. (1995) Use of a Real-Time RELAP5 Model to Dynamically Test a Digital Feedwater Control System for a Boiling Water Reactor. Nuclear Technology 111:2, pages 283-302.
Read now
Chun-Chang Chao, Chi Ta Chen & Min Lee. (1995) An Estimation of Core Damage Frequency of a Pressurized Water Reactor During Midloop Operation Due to Loss of Residual Heat Removal. Nuclear Technology 111:1, pages 23-33.
Read now

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Order Reprints Request Corporate Permissions

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

Request Academic Permissions

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.

Related research

People also read lists articles that other readers of this article have read.

Recommended articles lists articles that we recommend and is powered by our AI driven recommendation engine.

Cited by lists all citing articles based on Crossref citations.
Articles with the Crossref icon will open in a new tab.