Molten salt reactor core simulation with PROTEUS

Fei, T.; Feng, B.; Heidet, F.

doi:10.1016/j.anucene.2019.107099

Title: Molten salt reactor core simulation with PROTEUS

Abstract

The Nuclear Energy Advance Modeling and Simulation Program (NEAMS) of the US Department of Energy (DOE) aims to develop advanced simulation tools to aid the development of advanced nuclear technologies. The high-fidelity PROTEUS code was developed in the NEAMS program for reactor physics analysis. This paper tests the applicability of the PROTEUS code to simulate a Molten Salt Reactor (MSR). The OpenMC code based on the Monte Carlo Method was employed to generate the cross sections and to provide stochastic solutions for verification. The PROTEUS code was successfully employed to simulate the steady-state performance of an MSR represented by the ThorCon core design. The 2D lattice, 2D core, and 3D full core calculations performed by PROTEUS show good agreement with that predicted by OpenMC. Furthermore, for the nodal option within PROTEUS, the precursor drift model was also tested, and this effect resulted in a reduction of the k-eff by 300 pcm.

Authors:

Fei, T. ^[1]; Feng, B. ^[1]; Heidet, F. ^[1]

Argonne National Lab. (ANL), Argonne, IL (United States)

Publication Date:: 2019-10-23

Research Org.:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1632330

Alternate Identifier(s):: OSTI ID: 1701985

Grant/Contract Number:: AC02-06CH11357

Resource Type:: Accepted Manuscript

Journal Name:: Annals of Nuclear Energy (Oxford)

Additional Journal Information:: Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 140; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; High-fidelity; MSR; Neutronics; PROTEUS

Citation Formats


                    Fei, T., Feng, B., and Heidet, F.. Molten salt reactor core simulation with PROTEUS.  United States: N. p., 2019. 
Web.  doi:10.1016/j.anucene.2019.107099.

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                    Fei, T., Feng, B., & Heidet, F.. Molten salt reactor core simulation with PROTEUS.  United States.  https://doi.org/10.1016/j.anucene.2019.107099

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                    Fei, T., Feng, B., and Heidet, F.. Wed .  
"Molten salt reactor core simulation with PROTEUS".  United States.  https://doi.org/10.1016/j.anucene.2019.107099.  https://www.osti.gov/servlets/purl/1632330.

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@article{osti_1632330,

  title        = {Molten salt reactor core simulation with PROTEUS},

  author       = {Fei, T. and Feng, B. and Heidet, F.},

  abstractNote = {The Nuclear Energy Advance Modeling and Simulation Program (NEAMS) of the US Department of Energy (DOE) aims to develop advanced simulation tools to aid the development of advanced nuclear technologies. The high-fidelity PROTEUS code was developed in the NEAMS program for reactor physics analysis. This paper tests the applicability of the PROTEUS code to simulate a Molten Salt Reactor (MSR). The OpenMC code based on the Monte Carlo Method was employed to generate the cross sections and to provide stochastic solutions for verification. The PROTEUS code was successfully employed to simulate the steady-state performance of an MSR represented by the ThorCon core design. The 2D lattice, 2D core, and 3D full core calculations performed by PROTEUS show good agreement with that predicted by OpenMC. Furthermore, for the nodal option within PROTEUS, the precursor drift model was also tested, and this effect resulted in a reduction of the k-eff by 300 pcm.},

  doi          = {10.1016/j.anucene.2019.107099},

  journal      = {Annals of Nuclear Energy (Oxford)},

  number       = ,

  volume       = 140,

  place        = {United States},

  year         = {2019},

  month        = {10}

}

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Journal Article:

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https://doi.org/10.1016/j.anucene.2019.107099

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Cited by: 3 works

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Figures / Tables:

Table 1: PROTEUS solvers summary

All figures and tables (22 total)

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Works referenced in this record:

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
journal, December 2006

Chadwick, M. B.; Obložinský, P.; Herman, M.
Nuclear Data Sheets, Vol. 107, Issue 12
DOI: 10.1016/j.nds.2006.11.001

OpenMC: A state-of-the-art Monte Carlo code for research and development
journal, August 2015

Romano, Paul K.; Horelik, Nicholas E.; Herman, Bryan R.
Annals of Nuclear Energy, Vol. 82
DOI: 10.1016/j.anucene.2014.07.048

Figures / Tables found in this record:

Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.

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Title: Molten salt reactor core simulation with PROTEUS

Abstract

Citation Formats

Figures / Tables:

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology journal, December 2006

OpenMC: A state-of-the-art Monte Carlo code for research and development journal, August 2015

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
journal, December 2006

OpenMC: A state-of-the-art Monte Carlo code for research and development
journal, August 2015