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The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The estimation of spent nuclear fuel source term (decay heat, reactivity, nuclide inventory, etc.) has several sources of uncertainty such as uncertainties in nuclear data, uncertainties in the operation history, and choice ...
Validating the serpent-ants Calculation Chain Using BEAVRS Fresh Core Hot Zero Power Data
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The serpent Monte Carlo code and the serpent-ants two-step calculation chain are used to model the hot zero power physics tests described in the BEAVRS benchmark. The predicted critical boron concentrations, control rod ...