Kinetic parameters of a material test research reactor fueled with high density U3Si2 dispersion fuels

Author:

Muhammad Farhan,Majid Asad

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference14 articles.

1. Effect of updated WIMSD libraries on neutron energy spectrum at irradiation site of Pakistan Research Reactor-1 using 3D modelling;Ahmad;Annals of Nuclear Energy,2004

2. Effect of high-density fuel loading on criticality of low enriched uranium fueled material test research reactors;Ahmed;Annals of Nuclear Energy,2005

3. Relative Neutronic Performance of Proposed High-Density Dispersion Fuels in Water-moderated and D2O-reflected Research Reactors;Bretscher,1996

4. Prospectives on research reactor utilization;Dodd;Physica B,2002

5. Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1971. Nuclear reactor core analysis Code-CITATION, USAEC Report ORNL-TM-2496, Revision 2. Oak Ridge National Laboratory.

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