CFD analysis of suspended debris during postulated severe core damage accident of PHWR-Reference-Cited by-同舟云学术

CFD analysis of suspended debris during postulated severe core damage accident of PHWR

Published:2020-02 Issue: Volume:357 Page:110390
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Dutt Nitesh,Singh Ankit R.,Sahoo Pradeep K.

Funder

Bhabha Atomic Research Centre

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

Reference15 articles.

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3. Experimental investigation of transient behaviour of IPHWR under heat up condition;Dutt;Nucl. Eng. Des.,2015

4. Francis, N.D. Jr., Itamura, M.T., Webb, S.W., James, D.L., 2002.CFD Calculation of Internal Natural Convection in the Annulus between Horizontal Concentric Cylinders. Sand Report, Prepared by Sandia National Laboratories Albuquerque, New Mexico 871 85 and Livermore, California 94550.

5. Gupta, S.K., Dutta, B. K., Raj, V.V., 1996. A study of the Indian PHWR reactor channel under prolonged deteriorated flow conditions. Proceedings of a Technical committee meeting on advances in heavy water reactor technology; Mumbai (India); 29 Jan – 1 Feb 1996, 331–359.

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