Experimental simulation of asymmetric heat up of coolant channel under small break LOCA condition for PHWR-Reference-Cited by-同舟云学术

Experimental simulation of asymmetric heat up of coolant channel under small break LOCA condition for PHWR

Published:2013-02 Issue: Volume:255 Page:138-145
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Yadav Ashwini K.,Majumdar P.,Kumar Ravi,Chatterjee B.,Gupta Akhilesh,Mukhopadhyay D.

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

Reference12 articles.

1. Degraded cooling in a CANDU reactor;Brown;Nucl. Sci. Eng.,1984

2. An experimental investigation of heat transfer from a reactor fuel channel to surrounding water;Gillespie,1981

3. Prediction of pressure tube integrity for a small LOCA and total loss of emergency coolant injection in CANDU;Gulshani;Trans. Am. Nucl. Soc.,1987

4. A study of Indian PHWR reactor channel under prolonged deteriorated flow conditions;Gupta,1996

5. CANDU fuel development during severely degraded cooling: experimental results;Kohn,1985

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