Application of Monte Carlo Code Shift for MSBR Dose Rate Calculations

Yan Cao; Eva E. Davidson; Benjamin R. Betzler; Bo Feng

doi:10.13182/PHYSOR22-37646

Application of Monte Carlo Code Shift for MSBR Dose Rate Calculations

Yan Cao
, Eva E. Davidson
, Benjamin R. Betzler
, Bo Feng

Reactor and Nuclear Fuel Cycle Analysis

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

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.

Original language	English
Title of host publication	Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
Publisher	American Nuclear Society
Pages	804-813
Number of pages	10
ISBN (Electronic)	9780894487873
DOIs	https://doi.org/10.13182/PHYSOR22-37646
State	Published - 2022
Event	2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States Duration: May 15 2022 → May 20 2022

Publication series

Name	Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022

Conference

Conference	2022 International Conference on Physics of Reactors, PHYSOR 2022
Country/Territory	United States
City	Pittsburgh
Period	05/15/22 → 05/20/22

Funding

The submitted manuscript has been created by UChicago Argonne, LLC, Operator of Argonne National Laboratory (“Argonne”). Argonne, a .S. U Department of Energy Office of Science laboratory, is operated under Contract No. DE-AC02-06CH11357. The U.S. Government retains for itself, and others acting on its behalf, a paid-up nonexclusive, irrevocable worldwide license in said article to reproduce, prepare derivative works, distribute copies to the public, and perform publicly and display publicly, by or on behalf of the Government. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan. http://energy.gov/downloads/doe-public-access-plan. Oak Ridge National Laboratory’s contributions were supported under contract DE-AC05-00OR22725 with the U.S. Department of Energy. The direction and support of the U.S. DOE Office of Nuclear Energy NEAMS program is greatly appreciated. This work was developed under the NEAMS Application Drivers Molten Salt Reactor work package. This research made use of Idaho National Laboratory (INL) computing resources which are supported by the Office of Nuclear Energy of the US Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517. The authors express appreciation to the Shift development team for their technical support. The submitted manuscript has been created by UChicago Argonne, LLC, Operator of Argonne National Laboratory (“Argonne”). Argonne, a U.S. Department of Energy Office of Science laboratory, is operated under Contract No. DE-AC02-06CH11357. The U.S. Government retains for itself, and others acting on its behalf, a paid-up nonexclusive, irrevocable worldwide license in said article to reproduce, prepare derivative works, distribute copies to the public, and perform publicly and display publicly, by or on behalf of the Government. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan. http://energy.gov/downloads/doe-public-access-plan. Oak Ridge National Laboratory's contributions were supported under contract DE-AC05-00OR22725 with the U.S. Department of Energy. The direction and support of the U.S. DOE Office of Nuclear Energy NEAMS program is greatly appreciated. This work was developed under the NEAMS Application Drivers Molten Salt Reactor work package. This research made use of Idaho National Laboratory (INL) computing resources which are supported by the Office of Nuclear Energy of the US Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517. The authors express appreciation to the Shift development team for their technical support.

Keywords

DOE-NEAMS
FW-CADIS
MSBR
Shift
distributed fission source
ex-core neutron and gamma dose rates

Access to Document

10.13182/PHYSOR22-37646

Cite this

Cao, Y., Davidson, E. E., Betzler, B. R., & Feng, B. (2022). Application of Monte Carlo Code Shift for MSBR Dose Rate Calculations. In Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022 (pp. 804-813). (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022). American Nuclear Society. https://doi.org/10.13182/PHYSOR22-37646

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abstract = "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.",

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author = "Yan Cao and Davidson, \{Eva E.\} and Betzler, \{Benjamin R.\} and Bo Feng",

note = "Publisher Copyright: {\textcopyright} 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.; 2022 International Conference on Physics of Reactors, PHYSOR 2022 ; Conference date: 15-05-2022 Through 20-05-2022",

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Cao, Y, Davidson, EE, Betzler, BR & Feng, B 2022, Application of Monte Carlo Code Shift for MSBR Dose Rate Calculations. in Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022, American Nuclear Society, pp. 804-813, 2022 International Conference on Physics of Reactors, PHYSOR 2022, Pittsburgh, United States, 05/15/22. https://doi.org/10.13182/PHYSOR22-37646

Application of Monte Carlo Code Shift for MSBR Dose Rate Calculations. / Cao, Yan; Davidson, Eva E.; Betzler, Benjamin R. et al.
Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. American Nuclear Society, 2022. p. 804-813 (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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N2 - 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.

AB - 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.

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KW - distributed fission source

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Y2 - 15 May 2022 through 20 May 2022

ER -

Application of Monte Carlo Code Shift for MSBR Dose Rate Calculations

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