System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents
Xu Wu,Koroush Shirvan +1 more
TLDR
In this paper, the authors analyzed three station blackout (SBO) scenarios for a representative U.S. operating Boiling Water Reactor (BWR) based on Peach Bottom Atomic Power Station using system thermal-hydraulics code TRACE.About:
This article is published in Nuclear Engineering and Design.The article was published on 2020-01-01 and is currently open access. It has received 16 citations till now. The article focuses on the topics: Boiling water reactor & Nuclear reactor core.read more
Citations
More filters
Journal ArticleDOI
Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout
Zehua Guo,Zehua Guo,Ryan Dailey,Tangtao Feng,Yukun Zhou,Zhongning Sun,Michael L. Corradini,Jun Wang +7 more
TL;DR: In this article, an uncertainty analysis was employed to investigate the potential benefits of ATF Cr-coated-Zr cladding and canister for an unmitigated Short-Term Station Blackout (STSBO) sequence in a generic BWR plant using the MELCOR systems code.
Journal ArticleDOI
Implications of accident tolerant fuels on thermal-hydraulic research
TL;DR: In this article, the authors discuss the economic opportunities with ATF cladding lies within challenging the current conservative technical specifications and safety procedures and pairing with more cost-effective high density fuel forms.
Journal ArticleDOI
System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents
Yue Jin,Xu Wu,Koroush Shirvan +2 more
TL;DR: In this article, a quantitative evaluation of the performance of monolithic FeCrAl cladding and Cr-coated Zircaloy cladding has been performed for Pressurized Water Reactor (PWR) Station Blackout (SBO) accidents.
Journal ArticleDOI
Risk-Informed Safety Analysis for Accident Tolerant Fuels
TL;DR: In this paper, accident tolerant fuels (ATF) are tested by different nuclear vendors and research organizations, and their introduction into the U.S light water reactor fleet is planned for the second half of 2019.
Journal ArticleDOI
Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout
TL;DR: In this article, the performance of the proposed ATF concept of Cr-coated-Zircaloy is assessed using a generic Boiling Water Reactor MELCOR plant model considering a Short-term Station Blackout (STSBO) scenario.
References
More filters
Journal ArticleDOI
Accident tolerant fuels for LWRs: A perspective
Steven J. Zinkle,Steven J. Zinkle,Kurt A. Terrani,Jess C. Gehin,Larry J. Ott,Lance Lewis Snead +5 more
TL;DR: In this article, three general strategies for accident tolerant fuels are explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr Alloy cladding with an alternative oxidation resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.
Journal ArticleDOI
Accident tolerant fuel cladding development: Promise, status, and challenges
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
Journal ArticleDOI
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
TL;DR: In this paper, a comparison of a range of commercial and model alloys, conventional austenitic steels do not have sufficient oxidation resistance with only ∼18Cr-10Ni, and higher alloyed type 310 stainless steel is protective but Ni is not a desirable alloy addition for this application.
Journal ArticleDOI
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
TL;DR: In this paper, a set of model FeCrAl alloys containing 10−20Cr, 3−5Al, and 0−0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FecrAlY alloys.
Journal ArticleDOI
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
TL;DR: In this paper, the impact of fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions was analyzed. But the authors focused on the impact on the nuclear power station's fuel performance.
Related Papers (5)
System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents
Yue Jin,Xu Wu,Koroush Shirvan +2 more
Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings
Anil Gurgen,Koroush Shirvan +1 more