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

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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.
Publisher
ELSEVIER SCIENCE SA
Issue Date
2015-10
Language
English
Article Type
Article
Keywords

SILICON-CARBIDE; SIC/SIC COMPOSITES; IRRADIATION; OXIDATION; STEAM; PERFORMANCE; REACTORS; FIBER; MODEL

Citation

NUCLEAR ENGINEERING AND DESIGN, v.292, pp.1 - 16

ISSN
0029-5493
DOI
10.1016/j.nucengdes.2015.05.023
URI
http://hdl.handle.net/10203/203869
Appears in Collection
NE-Journal Papers(저널논문)
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