Failure probabilities of SiC clad fuel during a LOCA in public acceptable simple SMR (PASS)

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dc.contributor.authorLee, Youhoko
dc.contributor.authorKim, Ho Sikko
dc.contributor.authorNo, Hee-Cheonko
dc.date.accessioned2016-04-15T02:58:19Z-
dc.date.available2016-04-15T02:58:19Z-
dc.date.created2015-10-06-
dc.date.created2015-10-06-
dc.date.issued2015-10-
dc.identifier.citationNUCLEAR ENGINEERING AND DESIGN, v.292, pp.1 - 16-
dc.identifier.issn0029-5493-
dc.identifier.urihttp://hdl.handle.net/10203/203869-
dc.description.abstractStructural integrity of SiC clad fuels in reference Small Modular Reactors (SMRs) (NuScale, SMART, IRIS) and a commercial pressurized water reactor (PWR) are assessed with a multi-layered SiC cladding structural analysis code. Featured with low fuel pin power and temperature, SMRs demonstrate markedly reduced incore-residence fracture probabilities below similar to 10(-7), compared to those of commercial PWRs similar to 10(-6)-10(-1). This demonstrates that SMRs can serve as a near-term deployment fit to SiC cladding with a sound management of its statistical brittle fracture. We proposed a novel SMR named Public Acceptable Simple SMR (PASS), which is featured with 14 x 14 assemblies of SiC clad fuels arranged in a square ring layout. PASS aims to rely on radiative cooling of fuel rods during a loss of coolant accident (LOCA) by fully leveraging high temperature tolerance of SiC cladding. An overarching assessment of SiC clad fuel performance in PASS was conducted with a combined methodology (1) FRAPCON-SiC for steady-state performance analysis of PASS fuel rods, (2) computational fluid dynamics code FLUENT for radiative cooling rate of fuel rods during a LOCA, and (3) multi-layered SiC cladding structural analysis code with previously developed SiC recession correlations under steam environments for both steady-state and LOCA. The results show that PASS simultaneously maintains desirable fuel cooling rate with the sole radiation and sound structural integrity of fuel rods for over 36 days of a LOCA without water supply. The stress level of PASS fuel rods during LOCA is predominantly governed by the initial cold gap pressure; a decrease of the cold gas gap pressure is a handy design direction to assure structural safety margin for SiC cladding.-
dc.languageEnglish-
dc.publisherELSEVIER SCIENCE SA-
dc.subjectSILICON-CARBIDE-
dc.subjectSIC/SIC COMPOSITES-
dc.subjectIRRADIATION-
dc.subjectOXIDATION-
dc.subjectSTEAM-
dc.subjectPERFORMANCE-
dc.subjectREACTORS-
dc.subjectFIBER-
dc.subjectMODEL-
dc.titleFailure probabilities of SiC clad fuel during a LOCA in public acceptable simple SMR (PASS)-
dc.typeArticle-
dc.identifier.wosid000361145300001-
dc.identifier.scopusid2-s2.0-84934913229-
dc.type.rimsART-
dc.citation.volume292-
dc.citation.beginningpage1-
dc.citation.endingpage16-
dc.citation.publicationnameNUCLEAR ENGINEERING AND DESIGN-
dc.identifier.doi10.1016/j.nucengdes.2015.05.023-
dc.contributor.localauthorNo, Hee-Cheon-
dc.contributor.nonIdAuthorLee, Youho-
dc.type.journalArticleArticle-
dc.subject.keywordPlusSILICON-CARBIDE-
dc.subject.keywordPlusSIC/SIC COMPOSITES-
dc.subject.keywordPlusOXIDATION-
dc.subject.keywordPlusIRRADIATION-
dc.subject.keywordPlusSTEAM-
dc.subject.keywordPlusPERFORMANCE-
dc.subject.keywordPlusREACTORS-
dc.subject.keywordPlusFIBER-
dc.subject.keywordPlusMODEL-
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