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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.3
- 수록면
- 741 - 751 (11page)
- DOI
- https://doi.org/10.1016/j.net.2020.08.025
이용수
초록· 키워드
오류제보하기
There has been a deep interest in trying to find better-performing fuel clad motivated by the desire todecrease the likelihood of the reactor barrier failure like what happened in Fukushima in recent years. Inthis study, the effect of move towards accident tolerant fuel (ATF) cladding as the most attracting conceptfor improving reactor safety is investigated for SMART modular reactor. These reactors have less productioncost, short construction time, better safety and higher power density. The SiC and FeCrAl materialsare considered as the most potential candidate for ATF cladding, and the results are comparedwith Zircaloy cladding material from reactor physics point of view. In this paper, the calculations areperformed by generating PMAX library by DRAGON lattice physics code to be used for further reactorcore analysis by PARCS code. The differential and integral worth of control and safety rods, reactivitycoefficient, power and temperature distributions, and boric acid concentration during the cycle areanalyzed and compared from the conventional fuel cladding. The rod ejection accident (REA) is alsoperformed to study how the power changed in response to presence of the ATF cladding in the reactorcore. The key quantitative finding can be summarized as: 20 C (3%) decrease in average fuel temperature,33 pcm (3%) increase in integral rod worth and cycle length, 1.26 pcm/ C (50%) and 1.05 pcm/ C(16%) increase in reactivity coefficient of fuel and moderator, respectively.
목차
등록된 정보가 없습니다.
참고문헌 (36)
참고문헌 신청
L. J. Ott / 2014 / Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions q / J. Nucl. Mater 448:520~533
J. Huang / 2017 / The safety analysis of a small pressurized water reactor utilizing fully ceramic microencapsulated fuel / Nucl. Eng. Des 320:250~257
J. Chun / 2015 / Safety evaluation of accident-tolerant FCM fueled core with SiC-coated zircalloy cladding for design-basis-accidents and beyond DBAs / Nucl. Eng. Des 289:287~295
R. Liu / 2018 / Multiphysics modeling of accident tolerant fuelcladding U3Si2-FeCrAl performance in a light water reactor / Nucl. Eng. Des 330:106~116
S. J. Zinkle / 2014 / Accident tolerant fuels for LWRs : a perspective q / J. Nucl. Mater 448:374~379
J. Huang / 2017 / The safety analysis of a small pressurized water reactor utilizing fully ceramic microencapsulated fuel / Nucl. Eng. Des 320:250~257
J. Chun / 2015 / Safety evaluation of accident-tolerant FCM fueled core with SiC-coated zircalloy cladding for design-basis-accidents and beyond DBAs / Nucl. Eng. Des 289:287~295
R. Liu / 2018 / Multiphysics modeling of accident tolerant fuelcladding U3Si2-FeCrAl performance in a light water reactor / Nucl. Eng. Des 330:106~116
S. J. Zinkle / 2014 / Accident tolerant fuels for LWRs : a perspective q / J. Nucl. Mater 448:374~379
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