Neutronic calculations of the MTR-22 MW research reactor loaded with MOX (PuO 2 &amp;UO 2 ) Caramel fuel using the MCNP5 Code

Shaaban, Ismail; Albarhoum, M.

doi:10.1016/j.anucene.2016.03.020

Annals of Nuclear Energy

2016

DOI: 10.1016/j.anucene.2016.03.020

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Neutronic calculations of the MTR-22 MW research reactor loaded with MOX (PuO 2 &UO 2 ) Caramel fuel using the MCNP5 Code

Ismail Shaaban

M. Albarhoum

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Neutronic calculations of the MTR-22 MW research reactor loaded with MOX (PuO 2 &UO 2 ) Caramel fuel using the MCNP5 Code

Cited by 2 publications

References 5 publications

Introduction: Energy technologies and their role in our life

Introduction: Energy technologies and their role in our life

Mixed oxides in nuclear fuels

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