Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques

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M. Saldideh, M. Shayesteh and M. Eshghi. Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques[J]. Chinese Physics C, 2014, 38(8): 088201. doi: 10.1088/1674-1137/38/8/088201
M. Saldideh, M. Shayesteh and M. Eshghi. Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques[J]. Chinese Physics C, 2014, 38(8): 088201.  doi: 10.1088/1674-1137/38/8/088201 shu
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Received: 2013-09-11
Revised: 1900-01-01
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Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques

    Corresponding author: M. Saldideh,
    Corresponding author: M. Eshghi,

Abstract: 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.

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