A comparative study of the MATRA-LMR-FB calculation with the SABRE result for the flow blockage accident in the sodium cooled fast reactor-Reference-Cited by-同舟云学术

A comparative study of the MATRA-LMR-FB calculation with the SABRE result for the flow blockage accident in the sodium cooled fast reactor

Published:2011-12 Issue:12 Volume:241 Page:5225-5237
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chang W.P.,Ha K.S.,Suk S.D.,Jeong H.Y.

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

Reference16 articles.

1. Cockey, C.L., et al., 1987. PRISM Preliminary Safety Information Document, GEFR-00793. UC-87Ta.

2. Dobson, G.P., O’Neill, J.M., 1992. SABRE, User Guide for Version 4. RSSD 261, AEA Technology.

3. Fluid flow through packed columns;Ergun;Chem. Eng. Prog.,1952

4. Development of the MATRA-LMR-FB for flow blockage analysis in a LMR;Ha;Nucl. Eng. Technol.,2009

5. Hahn, D., 2002. Conceptual design of KALIMER. The 17th KAIF/KNS Annual Conference. Seoul, Korea, pp. 169–177.

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