Development of a safety analysis code for molten salt reactors-Reference-Cited by-同舟云学术

Development of a safety analysis code for molten salt reactors

Published:2009-12 Issue:12 Volume:239 Page:2778-2785
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Zhang Dalin,Qiu Suizheng,Su Guanghui

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

Reference18 articles.

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2. Numerical Initial Value Problems in Ordinary Differential Equation;Gear,1971

3. Progress in integrated study of molten salt actinide recycler and transmuter system;Ignatiev,2006

4. DYN1D-MSR dynamics code for molten salt reactors;Krepel;Ann. Nucl. Energy,2005

5. DYN3D-MSR spatial dynamics code for molten salt reactors;Krepel;Ann. Nucl. Energy,2007

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