Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference24 articles.
1. Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP;Alloni;Prog. in Nucl. Energy,2014
2. Verification of SuperMC for MNSRs core analysis: The case of Ghana Research Reactor-I;Baidoo;Ann. Nucl. Energy,2018
3. Bazzana S. P. and Márquez Damián J. I. 1995. “RA-6 (Reactor: Water reflected, water moderated U(19.77)3Si2-Al Fuel plates”. International Handbook of Evaluated Criticality Safety Benchmark Experiments, Volume-II, IEU-COMP-THERM-014. NEA/NSC/DOC/(95)03/II. Revised version of September 30, 2010.
4. Duderstadt, J.J., Hamilton, L.J. (1976). Nuclear Reactor Analysis. John Wiley & Sons, Inc. New York, NY, 1976, 650 pages.
5. Benchmarking verification of the control rod effects on the MTR core parameters using the MTR-PC and the MCNP codes throughout 3D core modeling and rod-drop experiment;Hedayat;Prog. Nucl. Energy,2016
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