2015
DOI: 10.2172/1179443
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Regulatory Technology Development Plan Sodium Fast Reactor. Mechanistic Source Term Development

Abstract: 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov.

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Cited by 20 publications
(47 citation statements)
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“…As mentioned above, the development of the MSR MST assessment capability discussed in this report builds on the successful MST evaluation of the sodium fast reactor (SFR) concept developed as part of the DOE Advanced Reactor Technology, Regulatory Technology Development Plan (Grabaskas et al, 2015, Grabaskas et al, 2016aand Grabaskas et al, 2016b. The general methodology for MSR MST is summarized in Figure 1.…”
Section: Objectives and Approachmentioning
confidence: 99%
“…As mentioned above, the development of the MSR MST assessment capability discussed in this report builds on the successful MST evaluation of the sodium fast reactor (SFR) concept developed as part of the DOE Advanced Reactor Technology, Regulatory Technology Development Plan (Grabaskas et al, 2015, Grabaskas et al, 2016aand Grabaskas et al, 2016b. The general methodology for MSR MST is summarized in Figure 1.…”
Section: Objectives and Approachmentioning
confidence: 99%
“…Iodine is the major halogen, and it is a fission product coming from the fuel or decay of its precursors, for example, Te. Iodine will form some iodide with other fission products (e.g., CsI) which can dissolve into the primary salt. Therefore, nearly all iodine isotopes remain in the salt in the form of I − instead of validation .…”
Section: Impurities Contamination Mechanisms and Available Removal mentioning
confidence: 99%
“…In FY14, an analysis by Argonne [1] identified the development of an SFR-specific MST methodology as an existing licensing gap with high regulatory importance and a potentially long lead-time to closure. This work was followed by an initial examination of the current state-of-knowledge regarding SFR source term development (ANL-ART-3 [2]), which reported several potential gaps. Among these were the potential inadequacies of current computational tools to properly model and assess the transport and retention of radionuclides during a metal fuel pool-type SFR core damage incident 1 .…”
Section: Objectivementioning
confidence: 99%
“…The trial MST analysis will focus on the consequences of a bounding beyond design-basis core damage accident for a metal fuel, pool-type SFR 2 . Accidents within this category may result in fuel pin failures or limited fuel melting, but a coolable core geometry, vessel integrity, and core submersion in sodium are maintained.…”
Section: Scopementioning
confidence: 99%
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