Simulation of uncontrolled loss of flow transients of a material test research reactor fuelled with low and high enriched uranium dispersion fuels

Author:

Muhammad Farhan

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference19 articles.

1. Analysis of reactivity induced accidents at Pakistan Research Reactor-1;Bokhari;Annals of Nuclear Energy,2002

2. Bokhari, I.H., Israr, M., Pervez, S., 1999. Thermal hydraulic and safety analyses for Pakistan Research Reactor-1. In: 22nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Budapest, Hungary.

3. Glaser, A., 2005. About the enrichment limit for research reactor conversion: why 20%? In: International Meeting on RERTR, Boston, Massachusetts.

4. Simulation of LOFA and RIA for the IEA-R1 research reactor using the code MERSAT;Hainoun;ANE,2008

5. Research Reactor Core Conversion from Use of High Enriched Uranium to Use Low Enriched Uranium Fuel Handbook;IAEA,1980

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