New recommendation for the thermal conductivity of irradiated (U, Pu)O2 fuels under fast reactor conditions. Comparison with recent experimental data-Reference-Cited by-同舟云学术

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New recommendation for the thermal conductivity of irradiated (U, Pu)O2 fuels under fast reactor conditions. Comparison with recent experimental data

Published:2023-04 Issue: Volume:577 Page:154326
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Bonev P.,Chauvin N.,Staicu D.,Dahms E.,Montagnier G.,Papaioannou D.,Dumas J-C.,Boukhris I.,Viallard I.^ORCID,Lainet M.,Lamontagne J.,Hanifi K.

Funder

H2020 Euratom

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Publisher

Elsevier BV

Subject

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

Reference47 articles.

1. ESNII+ project, FP7-Fission 2013, Grant agreement no: 605172.

2. R.J.M. Konings et al. R.E. Stoller, Comprehensive Nuclear Materials, vol. 2, Elsevier, 2020.

3. D. Staicu, ESNII+ : preparing ESNII for Horizon 2020 : deliverable D742 : properties measurements on irradiated fuels (NESTOR 3), sept. 2017.

4. Melting temperature and thermal conductivity of irradiated mixed oxide fuel;Yamamoto;J. Nucl. Mater.,1993

5. Thermal conductivity of (U, Pu)O2, mixed oxide fuel;Philipponneau;J. Nucl. Mater.,1992

Cited by 1 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. Uranium–plutonium–americium cation interdiffusion in polycrystalline (U,Pu,Am)O2±x mixed oxides;Journal of Nuclear Materials;2024-01

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