Application of Monte Carlo code SHIFT for MSBR dose rate calculations

Conference · Fri Jul 01 04:00:00 EDT 2022

OSTI ID:23178745

Cao, Yan; Feng, Bo ^[1]; Davidson, Eva E.; Betzler, Benjamin R. ^[2]

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1. Nuclear Science and Engineering Division, Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL (United States)
2. 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
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTERIZED SIMULATION
DOSE RATES
GAMMA RADIATION
MOLTEN SALT FUELED REACTORS
NEUTRON FLUENCE
RADIATION DOSES
S CODES
SOURCE TERMS