Assessment of MARS-GCR Code for a New Reactor Cavity Cooling System Design-Reference-Cited by-同舟云学术

Assessment of MARS-GCR Code for a New Reactor Cavity Cooling System Design

Published:2008-04 Issue:1 Volume:162 Page:92-106
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Cho Yun-Je¹,Cho Hyoung-Kyu²,Park Goon-Cherl¹

Affiliation:

1. Seoul National University, Department of Nuclear Engineering San 56-1, Shillim-dong, Kwanak-Gu, Seoul 151-742, Korea

2. Korea Atomc Energy Research Institute 150 Dukjin-Dong, Yuseong-gu, Daejeon 305-353, Korea

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT08-A3935

Reference17 articles.

1. “Heat Transport and Afterheat Removal for Gas Cooled Reactors under Accident Conditions,” IAEA-TECDOC-1163, International Atomic Energy Agency (2000).

2. Experiments on a Water Pool-Type Reactor Cavity Cooling System in a High-Temperature Gas-Cooled Reactor

3. W. J. LEE, S. W. BAE, and B. D. CHUNG, “Validation of One-Dimensional Module of MARS 2.1 Computer Code by Comparing with the RELAP5/MOD3.3 Developmental Results,” KAERI/TR-2411/2003, Korea Atomic Energy Research Institute (2003).

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1. Development of bubble departure and lift-off diameter models in low heat flux and low flow velocity conditions;International Journal of Heat and Mass Transfer;2011-07

2. Assessment of the MARS code for design of water pool-type reactor cavity cooling system in HTGR;Nuclear Engineering and Design;2011-05