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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 1 - 15 (15page)
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For a long time, a top priority in the nuclear industry was the safe, reliable, and economicoperation of light water reactors. However, the development of accident-tolerant fuel (ATF)became a hot topic in the nuclear research field after the March 2011 events at Fukushima,Japan. In Korea, innovative concepts of ATF have been developing to increase fuel safetyand reliability during normal operations, operational transients, and also accident events.
The microcell UO2 and high-density composite pellet concepts are being developed as ATFpellets. A microcell UO2 pellet is envisaged to have the enhanced retention capabilities ofhighly radioactive and corrosive fission products. High-density pellets are expected to beused in combination with the particular ATF cladding concepts. Two conceptsdsurfacemodifiedZr-based alloy and SiC composite materialdare being developed as ATF cladding,as these innovative concepts can effectively suppress hydrogen explosions and the releaseof radionuclides into the environment.
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참고문헌 (51)
참고문헌 신청
Y.H. Koo / 2014 / KAERI's development of LWR accidenttolerant fuel / Nucl. Technol 186:295~304
J. Carmack / 2013 / Overview of the U.S. DOE accident tolerant fuel development program / TopFuel 2013
B. Chang / 2013 / Development of Moalloy for LWR fuel cladding to enhance fuel tolerance to severe accidents / TopFuel 2013
I. Idarraga-Trujillo / 2013 / Assessment at CEA of coated nuclear fuel cladding for LWRs with increased margins in LOCA and beyond LOCA conditions / TopFuel 2013
H.G. Kim / Application of Coating Technology on Zr-based Alloy to Decrease High-temperature Oxidation, Zirconium in the Nuclear Industry STP 1543
J. Carmack / 2013 / Overview of the U.S. DOE accident tolerant fuel development program / TopFuel 2013
B. Chang / 2013 / Development of Moalloy for LWR fuel cladding to enhance fuel tolerance to severe accidents / TopFuel 2013
I. Idarraga-Trujillo / 2013 / Assessment at CEA of coated nuclear fuel cladding for LWRs with increased margins in LOCA and beyond LOCA conditions / TopFuel 2013
H.G. Kim / Application of Coating Technology on Zr-based Alloy to Decrease High-temperature Oxidation, Zirconium in the Nuclear Industry STP 1543
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Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code
Nuclear Engineering and Technology
2022 .07
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Development of FEMAXI-ATF for analyzing PCMI behavior of SiC cladded fuel under power ramp conditions
Nuclear Engineering and Technology
2024 .03
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An evaluation on in-pile behaviors of SiC f /SiC cladding under normal and accident conditions with updated FROBA-ATF code
Nuclear Engineering and Technology
2021 .04
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A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti 3 SiC 2 for ATF cladding
Nuclear Engineering and Technology
2020 .01
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Development of Innovative Light Water Reactor Nuclear Fuel Using 3D Printing Technology
Journal of the Korean Society for Precision Engineering
2016 .04
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ATF 피복관의 응력 및 변형률 계산을 위한 해석적 모델의 개발
대한기계학회 춘추학술대회
2017 .04
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Searching for the viability of using thorium-based accident-tolerant fuel for VVER-1200
Nuclear Engineering and Technology
2024 .01
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Research and Development Methodology for Practical Use of Accident Tolerant Fuel in Light Water Reactors
Nuclear Engineering and Technology
2016 .01
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Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials
Nuclear Engineering and Technology
2021 .01
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Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding
Nuclear Engineering and Technology
2016 .01
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광섬유센서를 이용한 사고 저항성핵연료 (ATF) 표면에서의 강제 대류 비등 열전달 실험
대한기계학회 춘추학술대회
2022 .04
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ATF 사용후핵연료의 붕괴열 평가
한국에너지학회 학술발표회
2022 .10
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SAICAS 를 이용한 사고저항성 핵연료 피복관 코팅 결착특성 분석
대한기계학회 춘추학술대회
2021 .04
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Development status of microcell UO3 pellet for accident-tolerant fuel
Nuclear Engineering and Technology
2018 .01
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Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance
Nuclear Engineering and Technology
2023 .01
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Monitoring of Fuel and Cladding Elongation in a Nuclear Fuel Rod
Journal of the Korean Society for Precision Engineering
2017 .07
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Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS
Nuclear Engineering and Technology
2021 .03
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냉각수 제어 밸브 일체형 ATF 열교환기 적용이 연비에 미치는 영향에 대한 연구
한국자동차공학회 춘계학술대회
2018 .06
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옵셋 핀 적용 판 형 ATF 열교환기 설계
한국자동차공학회 춘계학술대회
2017 .05
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Effect of Hydrogen on Mechanical Behavior of Zr-based Alloy Fuel Cladding at High Temperature
한국방사성폐기물학회 학술대회
2018 .01
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