Experimental study of voiding effects with thorium based MOX fuel cluster in Critical Facility-Reference-Cited by-同舟云学术

Experimental study of voiding effects with thorium based MOX fuel cluster in Critical Facility

Published:2022-11 Issue: Volume:398 Page:111973
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mallick Amod Kishore,Kumar Rajeev,Samanta Sudipta,Upreti Yogesh,Deo Kapil,Bhandari Deep,Kannan Umasankari,Shivakumar V.,Kumar Verma Sharad,De S.K.,Sharma Avaneesh

Funder

Office of Research Central, University of Washington

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

Reference11 articles.

1. Sub-space iteration based monte carlo scheme for simultaneous computation of multiple dominant k-eigenmodes and acceleration of fission source iterations;Amod Kishore Mallickand Anurag Gupta;Ann. Nucl. Energy,2022

2. A general description of the lattice code WIMS;Askew;British Nuclear Energy Society,1966

3. S S Bajaj and A.R. Gore, “The Indian PHWR”, Nuclear Engineering and Design, 236, p701-722 (2006).

4. Determination of Spectrum shaping factor in nuclear reactor AHWR-CF by Monte Carlo method for material characterization using neutrons”;Bhandari;Mater. Today,2021

5. PATMOC: A multi-group Monte Carlo code for neutron transport simulation;KishoreMallick;RPDD/EP/164,2018

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1. Design Considerations for Utilising Thorium in Advanced Energy Systems;Transactions of the Indian National Academy of Engineering;2024-03-22

2. Fabrication of crack-free oxidic thorium–cerium microspheres by an external gelation process;Annals of Nuclear Energy;2023-06