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DOE OSTI · 3013509

SCALE Shielding Calculations for Advanced Reactor Accident Scenarios

Radulescu, Georgeta [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000176641718)·Hartanto, Donny [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000295541111)·Bostelmann, Friederike [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000165968088)·Wieselquist, William A. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000222117395)
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Abstract

The study results presented in this paper demonstrate the capabilities of the SCALE computer code for non–light water reactor (non-LWR) radiation source term and shielding calculations in support of the U.S. Nuclear Regulatory Commission non-LWR fuel cycle demonstration project. Representative non-LWR types, including the sodium-cooled fast reactor (SFR), the molten salt reactor (MSR), and the heat pipe microreactor (HPMR), were analyzed to evaluate dose rates associated with postulated accident scenarios (SFR and MSR), reactor operation (MSR and HPMR), and fuel self-protecting characteristics (HPMR). New features were implemented in SCALE depletion codes to better simulate MSR operation.

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Radulescu, Georgeta [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000176641718), Hartanto, Donny [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000295541111), Bostelmann, Friederike [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000165968088), Wieselquist, William A. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000222117395). 2025-05-28. SCALE Shielding Calculations for Advanced Reactor Accident Scenarios. https://doi.org/10.1080/00295639.2025.2503125

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