Thermodynamic evaluation of the quaternary U–Pu–Zr–Fe system – assessment of cladding temperature limits of metallic fuel in a fast reactor-Reference-Cited by-同舟云学术

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Thermodynamic evaluation of the quaternary U–Pu–Zr–Fe system – assessment of cladding temperature limits of metallic fuel in a fast reactor

Published:2001-04 Issue:1-2 Volume:294 Page:123-129
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kurata Masaki,Nakamura Kinya,Ogata Takanari

Publisher

Elsevier BV

Subject

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

Reference11 articles.

1. T. Ogata, PhD thesis, Kyoto University, Kyoto, 2000

2. M. Kurata, T. Ogata, K. Nakamura, T. Ogawa, J. Alloys Comp. 271–273 (1998) 636

3. Experimental and thermodynamic assessment of the FeZr system

4. Thermodynamic assessment of the Pu-U, Pu-Zr, and Pu-U-Zr systems

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1. Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding;Journal of Nuclear Materials;2021-02

2. Actinide Alloy Phase Diagram;Comprehensive Nuclear Materials;2020

3. Fe-U-Zr Ternary Phase Diagram Evaluation;MSI Eureka;2019-12-30

4. Development of a CALPHAD Thermodynamic Database for Pu-U-Fe-Ga Alloys;Applied Sciences;2019-11-22

5. Metal Fuel–Cladding Interaction;Reference Module in Materials Science and Materials Engineering;2019

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