Study on the tritium behaviors in the VHTR system. Part 1. Development of tritium analysis code for VHTR and verification-Reference-Cited by-同舟云学术

Study on the tritium behaviors in the VHTR system. Part 1. Development of tritium analysis code for VHTR and verification

Published:2010-07 Issue:7 Volume:240 Page:1758-1767
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kim Eung S.,Oh Chang H.,Patterson Mike

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

1. Atomic Energy Society of Japan, 1982. Tritium no Kagaku, Atomic Energy Society of Japan, vol. 31 (in Japanese).

2. DOE, 2002. A Technology Roadmap for Generation-IV Nuclear Energy Systems, GIF-002-00, U.S.DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, December 2002.

3. Forsyth, N., 1974. Tritium production and distribution in High Temperature Gas Cooled Reactors: Tritium generation, retention, distribution, and environmental release in a national 1,500MW(th) HTR. O.E.C.D. High Temperature Reactor Project DRAGON, DP REPORT 905, October 1974.

4. Gainey, B.W., 1976. A Review of Tritium Behavior in HTGR Systems, GA A13461, General Atomic Company, April 30.

5. The MathWorks, 2009. MATLAB 7.8 User Guide.

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