Abstract
A MELCOR (Methods of Estimation of Leakages and Consequences of Releases) model for a realistic heat pipe microreactor (rHPMR) was developed as part of an effort to perform code-to-code comparison with BlueCRAB (the federal version of Comprehensive Reactor Analysis Bundle [CRAB]) and FATE (Facility Flow, Aerosol, Thermal, and Explosion). Advanced reactor licensees and the US Nuclear Regulatory Commission are expected to employ these codes for performing safety assessments and quantifying postulated releases, including for microreactors as a part of the license application and review activities. This effort is supported by the US Department of Energy's Microreactor Program with the intent to address knowledge gaps. It also includes developing potential demonstrations or example cases to improve understanding and provide insights for safety assessments. This paper discusses the efforts to assess an rHPMR using MELCOR, where the rHPMR represents Westinghouse's eVinci design. eVinci is a horizontal, prismatic block, heat pipe-cooled, tristructural-isotropic (TRISO)-fueled reactor. Specifically, model development and steady-state results using MELCOR are presented. Limitations with MELCOR's ability to model an rHPMR restricted full assessment of this example case. Limitations included an inability to model both TRISO fuel and heat pipes in combination and to model heat pipes in a horizontal orientation. An alternative approach was explored as a possible effective solution for modeling an rHPMR without explicitly using the heat pipe model. Future efforts will revisit this example with revised models that include realistic fuel, core, and heat pipe components.
| Original language | English |
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| Title of host publication | Proceedings of the 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025 |
| Publisher | American Nuclear Society |
| Pages | 256-263 |
| Number of pages | 8 |
| ISBN (Electronic) | 9780894482250 |
| DOIs | |
| State | Published - 2025 |
| Event | 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025 - Chicago, United States Duration: Jun 15 2025 → Jun 18 2025 |
Publication series
| Name | Proceedings of the 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025 |
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Conference
| Conference | 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025 |
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| Country/Territory | United States |
| City | Chicago |
| Period | 06/15/25 → 06/18/25 |
Funding
The authors would like to acknowledge the colleagues at Westinghouse and Sandia National Laboratories for their valuable guidance and support and the US Department of Energy Microreactor Program for sponsoring this work. Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DEAC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (https://www.energy.gov/doe-publicaccess-plan).
Keywords
- BlueCRAB
- MELCOR
- eVinci
- heat pipe microreactor
- microreactor