Application of Monte Carlo code SHIFT for MSBR dose rate calculations
- Nuclear Science and Engineering Division, Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL (United States)
- Oak Ridge National Laboratory, Oak Ridge, TN 37831-6283 (United States)
This paper presents a study that applied the Monte Carlo code SHIFT to calculate the radiological environment within a detailed Molten Salt Breeder Reactor (MSBR) model. It represents one of the first applications of the SHIFT code in stand-alone simulations for non-light water reactors to help demonstrate the code's potential uses in the design, licensing, and operation of advanced reactors. The radiological conditions of the MSBR were modeled when the reactor is at two different operation modes: normal full power and a drained state. The Forward Weighted-Consistent Adjoint Driven Importance Sampling (FW-CADIS) hybrid method in SHIFT was applied successfully to calculate the ex-core neutron and gamma dose rates for the MSBR at full power. Neutron and gamma dose rates within the drain cell were also calculated for the MSBR at the drained state by integrating the source terms obtained from an ORIGEN-S depletion calculation into the SHIFT simulation. The results indicate that in the drained state, the delayed gammas from the depleted fuel salt are the main contributors to the dose rates. (authors)
- Research Organization:
- American Nuclear Society - ANS, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23178745
- Resource Relation:
- Conference: PHYSOR 2022: International conference on physics of reactors, Pittsburg (United States), 15-20 May 2022; Other Information: Country of input: France; 11 refs.; Related Information: In: Proceedings of the international conference on physics of reactors - Physor 2022| 3701 p.
- Country of Publication:
- United States
- Language:
- English
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