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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 16 - 25 (10page)
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초록· 키워드
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In severe loss of coolant accidents (LOCA), similar to those experienced at Fukushima DaiichiandThreeMile IslandUnit 1, the zirconiumalloy fuel claddingmaterials are rapidlyheateddueto nuclear decay heating and rapid exothermic oxidation of zirconium with steam. Thisheating causes the cladding to rapidly react with steam, lose strength, burst or collapse, andgenerate large quantities of hydrogen gas. Although maintaining core cooling remains thehighest priority in accident management, an accident tolerant fuel (ATF) design may extendcoping and recovery time for operators to restore emergency power, and cooling, and achievesafe shutdown. An ATF is required to possess high resistance to steam oxidation to reducehydrogen generation and sufficient mechanical strength to maintain fuel rod integrity andcore coolability. The initiative undertaken by Electric Power Research Institute (EPRI) is todemonstrate the feasibility of developing an ATF cladding with capability to maintain itsintegrity in 1,200e1,500 C steam for at least 24 hours. This ATF cladding utilizes thin-walledMo-alloys coated with oxidation-resistant surface layers. The basic design consists of a thinwalledMo alloy structural tube with a metallurgically bonded, oxidation-resistant outerlayer. Two options are being investigated: a commercially available iron, chromium, andaluminum alloy with excellent high temperature oxidation resistance, and a Zr alloy withdemonstratedcorrosionresistance.Asthese composite claddingswill incorporate eithernoZr,or thin Zr outer layers, hydrogen generation under severe LOCA conditions will be greatlyreduced. Key technical challenges and uncertainties specific to Moalloy fuel cladding include:economic core design, industrial scale fabricability, radiation embrittlement, and corrosionand oxidation resistance during normal operation, transients, and severe accidents. Progressin each aspect has been made and key results are discussed in this document. In addition toassisting plants inmeeting LightWater Reactor (LWR) challenges, accident-tolerantMo-basedcladding technologies are expected to be applicable for use in high-temperature helium andmolten salt reactor designs, as well as nonnuclear high temperature applications.
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참고문헌 (9)
참고문헌 신청
B. Cheng / 2012 / Fuel behavior in severe accidents and Mo-alloy based cladding to improve accident tolerance
S. Bragg Sitten / 2014 / Application of MELCOR to ATF Concepts for Severe Accident Analysis / Presented at EPRI/INL/DOEWorkshop on Accident Tolerant Fuel
B. Cheng / 2015 / Feasibility evaluations of Mo-alloy cladding to enhance accident tolerance
2014 / IAEA Symposium on Accident Tolerant Fuel Concepts for Light Water Reactors
B.V. Cockeram / 2008 / Irradiation hardening in unalloyed and ODS molybdenum during low dose neutron irradiation at 300º C and 600º C / J. Nucl. Mater 382:1~23
S. Bragg Sitten / 2014 / Application of MELCOR to ATF Concepts for Severe Accident Analysis / Presented at EPRI/INL/DOEWorkshop on Accident Tolerant Fuel
B. Cheng / 2015 / Feasibility evaluations of Mo-alloy cladding to enhance accident tolerance
2014 / IAEA Symposium on Accident Tolerant Fuel Concepts for Light Water Reactors
B.V. Cockeram / 2008 / Irradiation hardening in unalloyed and ODS molybdenum during low dose neutron irradiation at 300º C and 600º C / J. Nucl. Mater 382:1~23
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