A model to predict thermal conductivity of irradiated U–Mo dispersion fuel-Reference-Cited by-同舟云学术

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A model to predict thermal conductivity of irradiated U–Mo dispersion fuel

Published:2016-05 Issue: Volume:473 Page:309-319
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Burkes Douglas E.,Huber Tanja K.,Casella Andrew M.

Funder

National Nuclear Security Administration Office

agency of the United States Government

Publisher

Elsevier BV

Subject

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

Reference30 articles.

1. Fuels for Research and Test Reactors;Stahl,1982

2. About the enrichment limit for research reactor conversion: why 20%?;Glaser,2005

3. Advanced Fuel Cycle and Reactor Concepts;International Atomic Energy Agency,1980

4. Behavior of fissionable material under irradiation;Boltax,1962

5. Interaction Layer Characteristics in U-xMo Dispersion/Monolithic Fuels;Porter,2010

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1. Numerical simulation method of the failure behavior of the UMo-Al monolithic fuel element;Frontiers in Energy Research;2024-07-09

2. Development of a hybrid model for fuel performance analysis of spherical fuel elements under normal conditions;Journal of Nuclear Materials;2023-05

3. Modeling of heat transfer in a fuel pellet based on uranium dioxide and ceramics (beryllium oxide);Kompleksnoe Ispolʹzovanie Mineralʹnogo syrʹâ/Complex Use of Mineral Resources/Mineraldik Shikisattardy Keshendi Paidalanu;2021-09-12

4. Thermal properties of U-Mo alloys irradiated under high fission power density;Journal of Nuclear Materials;2021-04

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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