DC Field | Value | Language |
---|---|---|
dc.contributor.author | Lee, Youho | ko |
dc.contributor.author | Kim, Ho Sik | ko |
dc.contributor.author | No, Hee-Cheon | ko |
dc.date.accessioned | 2016-04-15T02:58:19Z | - |
dc.date.available | 2016-04-15T02:58:19Z | - |
dc.date.created | 2015-10-06 | - |
dc.date.created | 2015-10-06 | - |
dc.date.issued | 2015-10 | - |
dc.identifier.citation | NUCLEAR ENGINEERING AND DESIGN, v.292, pp.1 - 16 | - |
dc.identifier.issn | 0029-5493 | - |
dc.identifier.uri | http://hdl.handle.net/10203/203869 | - |
dc.description.abstract | Structural 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.language | English | - |
dc.publisher | ELSEVIER SCIENCE SA | - |
dc.subject | SILICON-CARBIDE | - |
dc.subject | SIC/SIC COMPOSITES | - |
dc.subject | IRRADIATION | - |
dc.subject | OXIDATION | - |
dc.subject | STEAM | - |
dc.subject | PERFORMANCE | - |
dc.subject | REACTORS | - |
dc.subject | FIBER | - |
dc.subject | MODEL | - |
dc.title | Failure probabilities of SiC clad fuel during a LOCA in public acceptable simple SMR (PASS) | - |
dc.type | Article | - |
dc.identifier.wosid | 000361145300001 | - |
dc.identifier.scopusid | 2-s2.0-84934913229 | - |
dc.type.rims | ART | - |
dc.citation.volume | 292 | - |
dc.citation.beginningpage | 1 | - |
dc.citation.endingpage | 16 | - |
dc.citation.publicationname | NUCLEAR ENGINEERING AND DESIGN | - |
dc.identifier.doi | 10.1016/j.nucengdes.2015.05.023 | - |
dc.contributor.localauthor | No, Hee-Cheon | - |
dc.contributor.nonIdAuthor | Lee, Youho | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordPlus | SILICON-CARBIDE | - |
dc.subject.keywordPlus | SIC/SIC COMPOSITES | - |
dc.subject.keywordPlus | OXIDATION | - |
dc.subject.keywordPlus | IRRADIATION | - |
dc.subject.keywordPlus | STEAM | - |
dc.subject.keywordPlus | PERFORMANCE | - |
dc.subject.keywordPlus | REACTORS | - |
dc.subject.keywordPlus | FIBER | - |
dc.subject.keywordPlus | MODEL | - |
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