MCNP Calculations of Subcritical Fixed Source and Fission Multiplication Factors
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MCNP Calculations of Subcritical Fixed Source and Fission Multiplication Factors

Transactions of the American Nuclear Society, Vol.102, pp.503-505
06/17/2010

Abstract and subjects

Computer simulation Critical experiments Eigenvalues Energy distribution Energy of formation Fission Mathematical models Monte Carlo methods Multiplication Nuclear engineering Nuclear fission Nuclear power generation Nuclear reactor components Nuclear reactors Standards Steady state Summaries

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