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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.6
- 수록면
- 1,747 - 1,755 (9page)
- DOI
- https://doi.org/10.1016/j.net.2020.12.004
이용수
초록· 키워드
오류제보하기
This paper presents floating absorber for safety at transient (FAST) which is a passive safety device forsodium-cooled fast reactors with a positive coolant temperature coefficient. Working principle of theFAST makes it possible to insert negative reactivity passively in case of temperature rise or voiding ofcoolant. Behaviors of the FAST in conventional oxide fuel-loaded and metallic fuel-loaded SFRs areinvestigated assuming anticipated transients without scram (ATWS) scenarios. Unprotected loss of flow(ULOF), unprotected loss of heat sink (ULOHS), unprotected transient overpower (UTOP) and unprotectedchilled inlet temperature (UCIT) scenarios are simulated at end of life (EOL) conditions of the oxide andthe metallic SFR cores, and performance of the FAST to improve the reactor safety is analyzed in terms ofreactivity feedback components, reactor power and maximum temperatures of fuel and coolant. It isshown that FAST is able to improve the safety margin of conventional burner-type SFRs during ULOF,ULOHS, UTOP and UCIT.
목차
등록된 정보가 없습니다.
참고문헌 (11)
참고문헌 신청
P. Sciora / 2011 / Low void effect core design applied on 2400 MWth SFR reactor / Proceedings of ICAPP 2011
S.J. Kim / 2000 / A pan-shape transuranic burner core with a low sodium void worth / Ann. Nucl. Energy 27:435
Donny Hartanto / 2018 / A comparative physics study for an innovative sodium-cooled fast reactor(iSFR) / Int. J. Energy Res 42(1)
S. Qvist / 2014 / An autonomous reactivity control system for improved fast reactor safety / Ann. Nucl. Energy 77:32~47
M. Kambe / 2005 / Transient characteristics of RAPID highly automated fast reactor without any control rods / Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005 :47~55
S.J. Kim / 2000 / A pan-shape transuranic burner core with a low sodium void worth / Ann. Nucl. Energy 27:435
Donny Hartanto / 2018 / A comparative physics study for an innovative sodium-cooled fast reactor(iSFR) / Int. J. Energy Res 42(1)
S. Qvist / 2014 / An autonomous reactivity control system for improved fast reactor safety / Ann. Nucl. Energy 77:32~47
M. Kambe / 2005 / Transient characteristics of RAPID highly automated fast reactor without any control rods / Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005 :47~55
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