Subchannel thermal analysis of rod bundle cores-Reference-Cited by-同舟云学术

Subchannel thermal analysis of rod bundle cores

Published:1972-04 Issue:1 Volume:21 Page:35-45
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chelemer H.,Weisman J.,Tong L.S.

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.

1. Statistically Determined Engineering Hot-Channel Subfactors of a Parallel Rod-Bundle Core;Chelemer;Trans. ANS 3,1960

2. Engineering Hot-Channel Factors for Open-Lattice Cores;Chelemer;Nucleonics,1962

3. An Integral Calculation of Three-Dimensional Nuclear-Thermal-Hydraulic Interaction;Sha;Trans. ANS,1966

4. Flow Redistribution in an Open Lattice Core;Tong;WCAP-1645,1960

5. Experimental Measurement of Mixing in Parallel Flow Rod Bundles;Bell;WAPD-TH-381,1958

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