Subchannel analysis of a critical power test, using simulated BWR S × S fuel assembly-Reference-Cited by-同舟云学术

Subchannel analysis of a critical power test, using simulated BWR S × S fuel assembly

Published:1990-09 Issue:1-3 Volume:122 Page:235-254
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mitsutake T.,Terasaka H.,Yoshimura K.,Oishi M.,Inoue A.,Akiyama M.

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

Reference20 articles.

1. Application of multi-fluid model in dryout prediction;Saito,1983

2. Critical hear flux predictions in rod bundles;Kao;Nucl. Technol.,1983

3. A rod centered subchannel analysis with turbulent(enthalpy) mixing for critical heat flux prediction in rod clusters cooled by boiling water;Gaspari,1974

4. Parametric study of CHF data;Reddy,1983

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