CFD analysis of moderator flow and temperature fields inside a vertical calandria vessel of nuclear reactor-Reference-Cited by-同舟云学术

CFD analysis of moderator flow and temperature fields inside a vertical calandria vessel of nuclear reactor

Published:2015-06 Issue: Volume:287 Page:95-107
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kansal Anuj Kumar^ORCID,Joshi Jyeshtharaj B.,Maheshwari Naresh Kumar,Vijayan Pallippattu Krishnan

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

Reference21 articles.

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2. 3rd ISHMT – ASME Heat and Mass Transfer Conference;Dharne,1997

3. Tube bundle flows with the large eddy simulation technique in curvilinear coordinates;Hassan;Int. J. Heat Mass Transf.,2004

4. Status of physical and numerical modelling of CANDU moderator circulation;Huget,1989

5. Experimental and numerical modelling of combined forced and free convection in a complex geometry with internal heat generation;Huget,1990

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