Neutronic Performance in a Peaceful Nuclear Explosion Reactor

CHINESE JOURNAL OF COMPUTATIONAL PHYSICS ›› 2006, Vol. 23 ›› Issue (5): 589-593.

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Neutronic Performance in a Peaceful Nuclear Explosion Reactor

BAI Yun, PENG Xian-jue

Institute of Applied Physics and Computational Mathematics, Beijing 100088, China

Received:2005-05-10 Revised:2005-07-27 Online:2006-09-25 Published:2006-09-25

Abstract

Abstract: The neutronic behavior in a peaceful nuclear explosion reactor is analyzed.²³⁸U and ²³²Th are used in the reactor to produce fission materials,²³⁹Pu and ²³³U. MCNP is used to calculate thickness of the neutron slowing down material C₂H₄.The thickness of ²³²Th is predicted in which the neutron capturing ability is above 50%.Considering the effect of reflected saving,the thickness of ²³²Th is reduced.

Key words: neutron performance, peaceful nuclear explosive reactor, fusion explosions

CLC Number:

TL32

BAI Yun, PENG Xian-jue. Neutronic Performance in a Peaceful Nuclear Explosion Reactor[J]. CHINESE JOURNAL OF COMPUTATIONAL PHYSICS, 2006, 23(5): 589-593.

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Neutronic Performance in a Peaceful Nuclear Explosion Reactor

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