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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.11
- 수록면
- 3,517 - 3,527 (11page)
- DOI
- https://doi.org/10.1016/j.net.2021.05.013
이용수
초록· 키워드
오류제보하기
New 80-MW (electric) ultra-long-life sodium cooled fast reactor core having inherent safety characteristics is designed with heterogeneous fuel assemblies comprised of driver and blanket fuel rods. Severaloptions using upper sodium plenum and SSFZ (Special Sodium Flowing Zone) for reducing sodium voidreactivity are neutronically analyzed in this core concept in order to improve the inherent safety of thecore. The SSFZ allowing the coolant flow from the peripheral fuel assemblies increases the neutronleakage under coolant expansion or voiding. The Monte Carlo calculations were used to design the coresand analyze their physics characteristics with heterogeneous models. The results of the design andanalyses show that the final core design option has a small burnup reactivity swing of 618 pcm over ~54EFPYs cycle length and a very small sodium void worth of ~35pcm at EOC (End of Cycle), which leads tothe satisfaction of all the conditions for inherent safety with large margin based on the quasi-staticreactivity balance analysis under ATWS (Anticipated Transient Without Scram)
목차
등록된 정보가 없습니다.
참고문헌 (29)
참고문헌 신청
A. J. Kuperman / 2018 / Plutonium for Energy ? e Explaining the Global Decline of MOX, T / The University of Texas at Austin
K. Tucek / 2006 / Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects, severe safety and economical issues / Nucl. Eng. Des 236:1589~1598
W. S. YANG / 2012 / FAST REACTOR PHYSICS AND COMPUTATIONAL METHODS / Nuclear Engineering and Technology 44(2):177~198
T. K. Kim / 2010 / Fuel Cycle Analysis of Once-Through Nuclear Systems :Fuel Cycle Research & Development
W. You / 2016 / A core physics study of advanced sodium-cooled TRU burners with thorium-and uranium-based metallic fuels / Nucl. Technol 194:217~232
K. Tucek / 2006 / Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects, severe safety and economical issues / Nucl. Eng. Des 236:1589~1598
W. S. YANG / 2012 / FAST REACTOR PHYSICS AND COMPUTATIONAL METHODS / Nuclear Engineering and Technology 44(2):177~198
T. K. Kim / 2010 / Fuel Cycle Analysis of Once-Through Nuclear Systems :Fuel Cycle Research & Development
W. You / 2016 / A core physics study of advanced sodium-cooled TRU burners with thorium-and uranium-based metallic fuels / Nucl. Technol 194:217~232
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