Burnup study for Pakistan Research Reactor-1 utilizing high density low enriched uranium fuel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference19 articles.
1. Effect of new cross section evaluations on criticality and neutron energy spectrum of a typical material test research reactor;Ahmad;Ann. Nucl. Energy,2004
2. Effect of updated WIMSD libraries on Neutron energy spectrum at irradiation site of Pakistan Research Reactor-1 using 3D modeling;Ahmad;Ann. Nucl. Energy,2005
3. Effect of high-density fuel loading on criticality of low enriched uranium fueled material test research reactors;Ahmed;Ann. Nucl. Energy,2005
4. Arshad, M., 1990. Introduction to the Fuel Cycle Analysis Program FCAP, PINSTECH-117
5. Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel;Aslam;Ann. Nucl. Energy,2002
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1. A study on improving the performance of a research reactor's equilibrium core;Nuclear Technology and Radiation Protection;2013
2. Phase constituents of Al-rich U–Mo–Al alloys examined by transmission electron microscopy;Journal of Nuclear Materials;2009-11
3. Reactivity feedback coefficients of a material test research reactor fueled with high-density U3Si2 dispersion fuels;Nuclear Engineering and Design;2008-10
4. Utilization of high-density fuel and beryllium elements for the neutron flux enhancement in typical MTR type research reactors;Progress in Nuclear Energy;2007-04
5. A study of reduction in fuel requirement and enhancement of neutron flux in typical MTR type research reactors;Progress in Nuclear Energy;2007-03
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