Nuclear Science and Engineering / Volume 59 / Number 3 / March 1976 / Pages 205-214
Technical Paper / dx.doi.org/10.13182/NSE76-A26819
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A new and efficient Monte Carlo approach to the solution of the Dirichlet heat transfer problem is developed and implemented. The adaptability of this approach to Monte Carlo radiation transport codes is highly useful for problems that require both heat transfer and radiation transport calculations, e.g., analyses of nuclear reactor fuel shipping casks. Criticality, shielding, and heat transfer calculations can be performed with one geometric description and one computer code.