Diana — A fast and high capacity computer code for interchannel coolant mixing in rod arrays-Reference-Cited by-同舟云学术

Diana — A fast and high capacity computer code for interchannel coolant mixing in rod arrays

Published:1974-09 Issue:2 Volume:30 Page:214-222
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hirao Seizo,Nakao Noboru

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

Reference5 articles.

1. Cross-flow mixing between parallel flow channels during boiling, Part I, COBRA-Computer Program for Coolant Boiling in Rod Arrays;Rowe;BNWL-371 PTI,1967

2. A digital computer program for thermal-hydraulic subchannel analysis of rod bundle nuclear fuel elements;Rowe;BNWL-1229,1970

3. D.S. Rowe, COBRA-III: a digital computer program for steady state and transient thermal-hydraulic analysis of rod bundle nuclear fuel elements, BNWL-B-82.

4. COBRA-IIA, a program for thermal-hydaulic analysis in very large bundles of fuel pins;Wheeler;BNWL-1422, UC-32,1970

5. Channel deformation analysis for fast reactor fuel assemblies undergoing swelling and thermal bowing;Ohmae;Nucl. Eng. Des.,1972

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