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Neutronic calculations for CANDU thorium systems using Monte Carlo techniques
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作者 m.saldideh M.Shayesteh M.Eshghi 《Chinese Physics C》 SCIE CAS CSCD 2014年第8期111-115,共5页
In this paper, we have investigated the prospects of exploiting the rich world thorium reserves using Canada Deuterium Uranium (CANDU) reactors. The analysis is performed using the Monte Carlo MCNP code in order to ... In this paper, we have investigated the prospects of exploiting the rich world thorium reserves using Canada Deuterium Uranium (CANDU) reactors. The analysis is performed using the Monte Carlo MCNP code in order to understand how much time the reactor is in criticality conduction. Four different fuel compositions have been selected for analysis. We have obtained the infinite multiplication factor, k∞, under full power operation of the reactor over 8 years. The neutronic flux distribution in the full core reactor has already been investigated. 展开更多
关键词 CANDU reactors thorium oxide plutonium oxide MCNP code
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