Parameter studies of peak temperature rise for LMFBR blanket rod bundles-Reference-Cited by-同舟云学术

Parameter studies of peak temperature rise for LMFBR blanket rod bundles

Published:1982-04 Issue:3 Volume:68 Page:347-357
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Engel F.C.,Markley R.A.

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

Reference6 articles.

1. Characterization of heat transfer and temperature distributions in an electrically heated model of an LMFBR blanket assembly;Engel;Nucl. Engrg. Des.,1980

2. B. Minushkin, F.C. Engel, R.J. Atkins and R.A. Markley, Heat transfer tests of an electrically heated 7-rod mockup of an LMFBR radial blanket assembly, ASME Paper 75-WA/HT-80.

3. COBRA-IV-1: An interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores;Wheeler;BNWL-1962,1976

4. Mixing model for wire wrap fuel assemblies;Novendstern;Trans. Am. Nucl. Soc.,1972

5. Heat transfer test data of a 61-rod electrically heated LMFBR blanket assembly mockup and their use for subchannel code calibration, in Fluid Flow and Heat Transfer Over Rod or Tube Bundles;Engel,1979

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