Multiphysics Analysis System for Heat Pipe–Cooled Micro Reactors Employing PRAGMA-OpenFOAM-ANLHTP
Author:
Affiliation:
1. Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826, Korea
Funder
National Research Foundation of Korea
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2143209
Reference23 articles.
1. The Kilopower Reactor Using Stirling TechnologY (KRUSTY) Nuclear Ground Test Results and Lessons Learned
2. Design of megawatt power level heat pipe reactors
3. “OKLO Part II: Final Safety Analysis Report,” U.S. Nuclear Regulatory Commission (2020); https://www.nrc.gov/docs/ML2007/ML20075A003.pdf.
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1. Steady state neutronic and thermal–mechanical coupling analysis of inelastic deformation in solid-state heat pipe cooled reactor;Annals of Nuclear Energy;2024-12
2. Evaluation of Performance Research Nuclear Reactors' Steady-state and Kinetic Model Analyses;Annals of Civil and Environmental Engineering;2024-06-18
3. Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons;Frontiers in Energy Research;2024-02-06
4. Thermal Modeling of an eVinci™-like heat pipe microreactor using OpenFOAM;Nuclear Engineering and Design;2023-12
5. Multiphysics analysis of heat pipe cooled microreactor core with adjusted heat sink temperature for thermal stress reduction using OpenFOAM coupled with neutronics and heat pipe code;Frontiers in Energy Research;2023-06-05
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