Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel-Reference-Cited by-同舟云学术

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Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel

Published:2018-04 Issue: Volume:501 Page:31-44
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Cho Tae Won^ORCID,Kim Yeon Soo,Park Jong Man,Lee Kyu Hong,Kim Sunghwan^ORCID,Lee Chong Tak,Yang Jae Ho,Oh Jang Soo,Sohn Dong-Seong^ORCID

Funder

National Research Foundation of Korea (NRF) funded by the Ministry of Science, ICT & Future Planning

Publisher

Elsevier BV

Subject

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

Reference49 articles.

1. Uranium intermetallic fuels (U-Al, U-Si, U-Mo);Kim,2012

2. Review of 15 years of high-density low-enriched UMo dispersion fuel development for research reactors in Europe;Van den Berghe;Nucl. Eng. Technol.,2014

3. Initial assessment of radiation behavior of very-high-density low-enriched-uranium fuels;Hofman,1999

4. High Density Fuel Development for Research Reactors, Proc. Inter. Meeting on RERT-2007;Lemoine,2007

5. The LEONIDAS and US partnership for UMo dispersion fuel qualification;Koonen,2009

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1. Multiphysics fuel performance modeling of dispersed TRISO-coated particle fuel plate under long-time normal condition and accident conditions;Nuclear Engineering and Design;2023-12

2. The studies of electronic structure, mechanical properties and ideal fracture behavior of U3Si1.75Al0.25: first-principle investigations;Journal of Materials Research and Technology;2021-11

3. Microstructure investigations of temperature effect on Al-UMo diffusion couples irradiated by swift Xe ions;Journal of Nuclear Materials;2021-04

4. A critical review of the microstructure of U–Mo fuels;Journal of Nuclear Materials;2020-11

5. Thermal conductivity measurement of the interaction layer between UMo and Al produced by high-energy heavy ion irradiation;Journal of Nuclear Materials;2020-10

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