Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon-Reference-Cited by-同舟云学术

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Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon

Published:2020-12 Issue:12 Volume:52 Page:2760-2770
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Jha Alok,Gupta Anurag,Das Rajarshi,Paraswar Shantanu D.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference30 articles.

1. Gap Conductance in Zircaloy-Clad Lwr Fuel Rods;Ainscough,1982

2. Fuel Design Analysis Code - FUDA;Das;PPED internal report, IAEA TecDoc,1981

3. Uranium dioxide thermal conductivity;Christensen;Trans. Am. Nucl. Soc.,1964

4. A method of correlating forced convection heat-transfer data and a comparison with fluid friction;Colburn;Int. J. Heat Mass Tran.,1964

5. Modification in the FUDA computer code to predict fuel performance at high burnup;Das;International Atomic Energy Agency (IAEA),1997

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1. Development of a coupled neutronics-CFD system for 540 MWE Indian Pressurized heavy water reactors (IPHWRs) and verification with slow online refuelling transient;Nuclear Engineering and Design;2023-08

2. Plenum Gas Effect on Fuel Temperature;Nuclear Reactors - Spacecraft Propulsion, Research Reactors, and Reactor Analysis Topics;2022-09-14

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