Development status of microcell UO3 pellet for accident-tolerant fuel

김동주; 김건식; 김동석; 오장수; 김종훈; 양재호; 구양현

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자료유형: 학술저널

저자정보: 김동주 김건식 김동석 오장수 김종훈 양재호 구양현

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제50권 제2호

발행연도: 2018.1

수록면: 253 - 258 (6page)

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A microcell UO2 pellet, as an accident-tolerant fuel pellet, is being developed to enhance the accidenttolerance of nuclear fuels under accident conditions as well as the fuel performance under normaloperation conditions. Improved capture-ability for highly radioactive and corrosive fission product (Cs and I) is the distinctfeature of a ceramic microcell UO2 pellet, and the enhanced pellet thermal conductivity is that of ametallic microcell UO2 pellet. The fuel temperature can be effectively decreased by enhanced thermalconductivity. In this study, the material concepts of metallic and ceramic microcell UO2 pellets were designed, andthe fabrication process of microcell UO2 pellets embodying the designed concept was developed. Wesuccessfully implemented the microcell UO2 pellets and produced microcell UO2 pellets. In addition, an assessment of the out-of-pile properties of a microcell UO2 pellet was performed, andthe in-reactor performance and behavior of the developed microcell pellets were evaluated through aHalden irradiation test. According to the expectations, the excellent performance of the microcell UO2pellets was confirmed by the online measurement data of the Halden irradiation test.

참고문헌 (17)

참고문헌 신청

I. Younker / 2016 / Neutronic evaluation of coating and cladding materials for accident tolerant fuels / Prog. Nucl. Energy 88:10~18

M.Q. Awan / 2017 / Neutronic design and evaluation of a PWR fuel assembly with accident tolerant-fully ceramic micro-encapsulated (AT-FCM) fuel / Nucl. Eng. Des. 319:126~139

K.D. Johnson / 2016 / Fabrication and microstructural analysis of UN-$U_3Si_2$ composites for accident tolerant fuel applications / J. Nucl. Mater. 477:18~23

C.P. Deck / 2015 / Characterization of SiC-SiC composites for accident tolerant fuel cladding / J. Nucl. Mater. 466:667~681

X. Wu / 2015 / Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions / Ann. Nucl. Energy 85:763~775

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