Multiphysics Coupling Methods for Molten Salt Reactor Modeling and Simulation in VERA-Reference-Cited by-同舟云学术

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Multiphysics Coupling Methods for Molten Salt Reactor Modeling and Simulation in VERA

Published:2021-05-03 Issue:10 Volume:195 Page:1065-1086
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Graham Aaron M.¹^ORCID,Taylor Zack²^ORCID,Collins Benjamin S.¹^ORCID,Salko Robert K.¹^ORCID,Poschmann Max³

Affiliation:

1. Oak Ridge National Laboratory, Reactor and Nuclear Systems Division, 1 Bethel Valley Road, P.O. Box 2008, MS-6172, Oak Ridge, Tennessee 37831-6172

2. University of Tennessee, 1412 Circle Drive, Knoxville, Tennessee

3. Ontario Tech University, 2000 Simcoe Street North, Oshawa, Ontario L1G 0C5, Canada

Funder

Oak Ridge National Laboratory

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2021.1901000

Reference17 articles.

1. The Virtual Environment for Reactor Applications (VERA): Design and architecture

2. “Virtual Environment for Reactor Applications,” Oak Ridge National Laboratory; https://vera.ornl.gov/ (current as of Sep. 28, 2020).

3. Consortium for Advanced Simulation of Lightwater Reactors https://casl.gov (current as of Sep. 28, 2020).

4. VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion

5. Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT

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1. CAD and constructive solid geometry modeling of the Molten Salt Reactor Experiment with OpenMC;Frontiers in Nuclear Engineering;2024-05-09

2. A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification;Progress in Nuclear Energy;2023-08

3. Depletion-driven thermochemistry of molten salt reactors: review, method, and analysis;Frontiers in Nuclear Engineering;2023-06-20

4. Plutonium Signatures in Molten-Salt Reactor Off-Gas Tank and Safeguards Considerations;Journal of Nuclear Engineering;2023-05-18

5. FERMI: Fusion Energy Reactor Models Integrator;Fusion Science and Technology;2023-03-20

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