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