Numerical modeling of the thermal behavior of a severely damaged core of PHWR under accident condition

Author:

Ajay Ketan,Kumar Ravi,Gupta Akhilesh

Publisher

Elsevier BV

Subject

Condensed Matter Physics,General Chemical Engineering,Atomic and Molecular Physics, and Optics

Reference62 articles.

1. Analysis of Severe Accidents in Pressurized Heavy Water Reactors, Vienna, Austria;IAEA,2008

2. A study of the Indian PHWR reactor channel under prolonged deteriorated flow conditions (No. IAEA-TECDOC--984);Gupta,1997

3. Study of ballooning of a completely voided pressure tube of Indian PHWR under heat up condition;Nandan;Nucl. Eng. Des.,2012

4. Experimental investigation on circumferential and axial temperature gradient over fuel channel under LOCA;Yadav;Heat Mass Transf.,2014

5. Full length channel pressure tube sagging under completely voided full length pressure tube of an Indian PHWR;Negi;Nucl. Eng. Des.,2017

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