Numerical and experimental investigation on thermal expansion of UO2-5 vol% Mo microcell pellet for qualitative comparison to UO2 pellet-Reference-Cited by-同舟云学术

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Numerical and experimental investigation on thermal expansion of UO2-5 vol% Mo microcell pellet for qualitative comparison to UO2 pellet

Published:2019-05 Issue: Volume:518 Page:342-349
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Lee Heung Soo^ORCID,Kim Dong-Joo,Yang Jae Ho,Kim Dong Rip^ORCID

Funder

Korea Institute of Energy Technology Evaluation and Planning

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference36 articles.

1. Neutronic evaluation of coating and cladding materials for accident tolerant fuels;Younker;Prog. Nucl. Energy,2016

2. Microencapsulated fuel technology for commercial light water and advanced reactor application;Terrani;J. Nucl. Mater.,2012

3. Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3Si2) with increased uranium loading;Ortega;J. Nucl. Mater.,2016

4. Oxide Fuels, Nuclear Materials Part 1, Materials Science and Technology;Lambert,1994

5. Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets;Kim;J. Nucl. Mater.,2006

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Development of thermal conductivity model with use of a thermal resistance circuit for metallic UO2 microcell nuclear fuel pellets;Nuclear Engineering and Technology;2023-10

2. Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions;Journal of Nuclear Materials;2021-12

3. In-situ synthesized nanocrystalline UO2/SiC composite with superior thermal conductivity;Ceramics International;2021-11

4. Thermodynamic Evaluation of Equilibrium Oxygen Composition of UO2-Mo Nuclear Fuel Pellet Under High Temperature Steam;Frontiers in Energy Research;2021-07-22

5. Fabrication of UO2-BeO composite pellets with superior thermal conductivity based on multi-parameter theoretical analyses;Journal of Nuclear Materials;2020-12

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