Temperature and composition dependent thermal conductivity model for U-Zr alloys-Reference-Cited by-同舟云学术

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Temperature and composition dependent thermal conductivity model for U-Zr alloys

Published:2018-08 Issue: Volume:507 Page:360-370
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Chen Weiming,Bai Xian-Ming

Funder

U.S. Department of Energy, Nuclear Energy University Program

Purdue University

Battelle Energy Alliance

Faculty Joint Appointment Program

U.S. Department of Energy

Publisher

Elsevier BV

Subject

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

Reference34 articles.

1. 3.01-Metal fuel;Ogata,2012

2. A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents

3. Swelling behavior of U-Pu-Zr fuel

4. 3.15-Metal fuel-cladding interaction;Keiser,2012

5. Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9

Cited by 21 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. The Effect of Niobium on the Mechanical and Thermodynamic Properties of Zirconium Alloys;Metals;2024-05-29

2. Calculation of the effective thermal conductivity of porous polycrystalline U-10Mo alloy based on phase-field simulation;Nuclear Engineering and Design;2023-11

3. The initial oxidation behavior of a UCxN1-x layer prepared by the pulsed laser ablation in the 1:1 N2+CH4 atmosphere;Journal of Nuclear Materials;2023-10

4. Porosity effect on the thermal and mechanical properties of U-50Zr alloy: A molecular dynamics study;Journal of Nuclear Materials;2023-10

5. New fuel types for thermal reactors in LOCA conditions;Atomic Energy;2023-05

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