2021
DOI: 10.2172/1812897
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A Pathway for the Development of Advanced Reactor Mechanistic Source Term Modeling and Simulation Capabilities

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Cited by 8 publications
(24 citation statements)
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“…The report will be coordinated with respective modelers and industry stakeholders that may utilize this information in system, severe accident, or mechanistic source term analysis tools. The importance of "graphite dust" formation and transport to HTGR MST analyses has been highlighted previously [1] based on the effectiveness of carbonaceous compounds to absorb radionuclides. Therefore, it is necessary to understand the phenomenon of "graphite dust" formation in HTGR systems, due to friction between fuel pebbles and/or erosion of carbonaceous fuel or moderator matrices.…”
Section: Radionuclide Transport In Core Materialsmentioning
confidence: 99%
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“…The report will be coordinated with respective modelers and industry stakeholders that may utilize this information in system, severe accident, or mechanistic source term analysis tools. The importance of "graphite dust" formation and transport to HTGR MST analyses has been highlighted previously [1] based on the effectiveness of carbonaceous compounds to absorb radionuclides. Therefore, it is necessary to understand the phenomenon of "graphite dust" formation in HTGR systems, due to friction between fuel pebbles and/or erosion of carbonaceous fuel or moderator matrices.…”
Section: Radionuclide Transport In Core Materialsmentioning
confidence: 99%
“…The near-term tasks that have been outlined and recommended recently [1] to resolve modeling gaps in mechanistic source term analysis of HTGRs are discussed below in more detail. The gaps are briefly reviewed and the recommended actions to close these technical gaps are discussed in the context of similar ongoing work, existing mod/sim tools within NEAMS or otherwise, and crosscutting areas of other DOE research programs.…”
Section: Htgrmentioning
confidence: 99%
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“…To assist the advanced reactor industry, including liquid-fueled MSR vendors, the U.S Department of Energy (DOE) Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is pursuing the enhancement of MST modeling and simulation capabilities. Previous efforts as part of this project have examined key needs and outlined high priority tasks to accomplish the long-term development goals of the program [1][2][3][4]. Establishing the current state of knowledge regarding fuel salt aerosol and bubble behavior, which is examined in the current work, was identified as a high priority development item for MSR designs.…”
Section: Introductionmentioning
confidence: 99%