Assessment of the safety impact caused by the variations of the critical position of control rods and by the presence of an in-core flux trap on the power peaking factors in an MTR-type research reactor

Author:

Mazrou HakimORCID,Lababsa Djahid,Mokhtari Ourida

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

Reference24 articles.

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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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