Phenomena, gaps, and issues for neutronics modeling and simulation of FHRs
Abstract
On the path to deployment of any reactor, modeling tool verification and validation is a key step. Fluoride-Salt-Cooled High Temperature Reactors (FHR) pose challenges to neutronics modeling and simulation tools due to several design features of the reactor type. This paper presents a categorized list of phenomena that pose challenges to FHR modeling using current neutronics tools. These phenomena are presented in four categories: Fundamental Cross Section Data, Material Composition, Computational Methodology, and General Depletion. Here, a short path forward for these phenomena is also presented. In addition, a discussion of the resulting gaps in current codes is presented.
- Authors:
-
- Georgia Inst. of Technology, Atlanta, GA (United States)
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Canadian Nuclear Safety Commission, Ottawa, ON (Canada)
- Publication Date:
- Research Org.:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); Nuclear Regulatory Commission/Non-NUREG; USDOE
- OSTI Identifier:
- 1482094
- Alternate Identifier(s):
- OSTI ID: 1636406
- Report Number(s):
- BNL-209441-2018-JAAM
Journal ID: ISSN 0306-4549
- Grant/Contract Number:
- SC0012704
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Annals of Nuclear Energy (Oxford)
- Additional Journal Information:
- Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 123; Journal Issue: C; Journal ID: ISSN 0306-4549
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 42 ENGINEERING; Phenomena Identification and Ranking; PIRT; Fluoride-Salt-Cooled High Temperature Reactors (FHR); Modeling and Simulation Gaps
Citation Formats
Rahnema, Farzad, Diamond, David, Serghiuta, Dumitru, and Burke, Paul. Phenomena, gaps, and issues for neutronics modeling and simulation of FHRs. United States: N. p., 2018.
Web. doi:10.1016/j.anucene.2018.08.035.
Rahnema, Farzad, Diamond, David, Serghiuta, Dumitru, & Burke, Paul. Phenomena, gaps, and issues for neutronics modeling and simulation of FHRs. United States. https://doi.org/10.1016/j.anucene.2018.08.035
Rahnema, Farzad, Diamond, David, Serghiuta, Dumitru, and Burke, Paul. Tue .
"Phenomena, gaps, and issues for neutronics modeling and simulation of FHRs". United States. https://doi.org/10.1016/j.anucene.2018.08.035. https://www.osti.gov/servlets/purl/1482094.
@article{osti_1482094,
title = {Phenomena, gaps, and issues for neutronics modeling and simulation of FHRs},
author = {Rahnema, Farzad and Diamond, David and Serghiuta, Dumitru and Burke, Paul},
abstractNote = {On the path to deployment of any reactor, modeling tool verification and validation is a key step. Fluoride-Salt-Cooled High Temperature Reactors (FHR) pose challenges to neutronics modeling and simulation tools due to several design features of the reactor type. This paper presents a categorized list of phenomena that pose challenges to FHR modeling using current neutronics tools. These phenomena are presented in four categories: Fundamental Cross Section Data, Material Composition, Computational Methodology, and General Depletion. Here, a short path forward for these phenomena is also presented. In addition, a discussion of the resulting gaps in current codes is presented.},
doi = {10.1016/j.anucene.2018.08.035},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 123,
place = {United States},
year = {2018},
month = {9}
}
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Cited by: 5 works
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Figures / Tables:
Figure 1: AHTR Core (Varma, et. al., 2012)
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Works referenced in this record:
Generalized Energy Condensation Theory
journal, September 2008
- Rahnema, Farzad; Douglass, Steven; Forget, Benoit
- Nuclear Science and Engineering, Vol. 160, Issue 1
A stylized 3D Advanced High Temperature Reactor (AHTR) benchmark problem
journal, October 2018
- Zhang, Dingkang; Rahnema, Farzad
- Annals of Nuclear Energy, Vol. 120
Continuous-energy COMET solution to the stylized AHTR benchmark problem
journal, November 2018
- Zhang, Dingkang; Rahnema, Farzad
- Annals of Nuclear Energy, Vol. 121
Thermal neutron scattering cross section of liquid FLiBe
journal, November 2017
- Zhu, Y.; Hawari, A. I.
- Progress in Nuclear Energy, Vol. 101
Works referencing / citing this record:
Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR ZPR - LFR analysis
journal, December 2018
- Margulis, Marat; Blaise, Patrick; Gilad, Erez
- International Journal of Energy Research, Vol. 43, Issue 2
Figures / Tables found in this record:
Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.