Effect of PT/CT contact on the circumferential temperature distribution over a fully voided nuclear channel of IPHWR
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference13 articles.
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3. Experimental investigation on circumferential and axial temperature gradient over fuel channel under LOCA;Yadav;Heat Mass Transf.,2014
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5. Thermal analysis of severe channel damage caused by a stagnation channel break in PHWR;Mukhopadhyay;J. Press. Vessel Technol.,2002
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1. Influence of moderator temperature on fuel channel behaviour under PT-CT contact during LOCA for Indian PHWR;Annals of Nuclear Energy;2024-10
2. Numerical study on the effect of moderator depletion on thermal behaviour of fully voided 220 MWe IPHWR channel during LOCA;Nuclear Engineering and Design;2024-04
3. Numerical Investigation on Heat Flux Variation in Fuel Bundle Over Fully Voided Concentric Channel of IPHWR Under Severe Accidental Scenario;Journal of Thermal Science and Engineering Applications;2023-03-29
4. Numerical investigation on heat flux variation in fuel bundle on circumferential temperature over fully voided channel of IPHWR;LOW RADIOACTIVITY TECHNIQUES 2022 (LRT 2022): Proceedings of the 8th International Workshop on Low Radioactivity Techniques;2023
5. Numerical investigations on boiling of moderator during PT/CT contact in 220 MWe IPHWR under postulated accidental scenario;Nuclear Engineering and Design;2022-10
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