Investigation of burnup and temperature effects on the grain size of UO2 fuel along fission gas behavior

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
A. Sadeghnoedoost, A. Zolfaghari, A.S. Shirani
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引用次数: 0

Abstract

The fuel rod behavior at high burnups is in the center of attention and a clear trend over the last decades toward increasing fuel burnup in light water reactors can be observed. The implications of this initiative, however, have not been fully explored; hence the practical issues for high-burnup PWR fuels are needed for more treatment. The aim of this paper is to investigate the specific features of the high burnup structure and temperature of the irradiated nuclear fuel on grain size variation and fission gas behavior and to explore the various relevant parameters. In order to evaluate fission gases behavior such as intra-granular gas diffusion, inter-granular gas bubble growth, bubble coalescence and rate of fission gases release a program called SS is developed; and the grain growth models with temperature in low and high burnup are included to fission gas behavior in the program and obtained results compared with published data in literature; the comparison indicates results are in good agreement with each other in low burnup; however, in high burnup and low temperature region (HBS)1 more experience and investigations are needed to exploit discrepancies.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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