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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.3
- 수록면
- 920 - 926 (7page)
- DOI
- https://doi.org/10.1016/j.net.2020.07.042
이용수
초록· 키워드
오류제보하기
Capsules containing NaCleMgCl2 salt with 316L stainless steel or alloy N samples were irradiated in theOhio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel wasdesigned for this purpose, and details on its design and construction are given. Stainless steel samplesthat were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work showsa method for conducting in-reactor irradiationecorrosion experiments in static molten salts and presentspreliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloridesalts
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참고문헌 (26)
참고문헌 신청
S. Delpech / 2009 / Reactor physic and reprocessing scheme for innovative molten salt reactor system / J. Fluor. Chem 130(1):11~17
Charles W. Forsberg / 2008 / Design options for the advanced high-temperature reactor / Proceedings of ICAPP 8
C. W. Forsberg / 2007 / Liquid salt applications and molten salt reactors / Revue Gen erale du Nucl eaire 4:63
V. Ignatiev / 2014 / Molten salt actinide recycler and transforming system without and with TheU support : fuel cycle flexibility and key material properties / Ann. Nucl. Energy 64:408~420
V. Ignatiev / 2017 / Structural Materials for Generation IV Nuclear Reactors / Elsevier :153~189
Charles W. Forsberg / 2008 / Design options for the advanced high-temperature reactor / Proceedings of ICAPP 8
C. W. Forsberg / 2007 / Liquid salt applications and molten salt reactors / Revue Gen erale du Nucl eaire 4:63
V. Ignatiev / 2014 / Molten salt actinide recycler and transforming system without and with TheU support : fuel cycle flexibility and key material properties / Ann. Nucl. Energy 64:408~420
V. Ignatiev / 2017 / Structural Materials for Generation IV Nuclear Reactors / Elsevier :153~189
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