Thermodynamic database on U-Pu-Zr-Np-Am-Fe alloy system II — Evaluation of Np, Am, and Fe containing systems--Reference-Cited by-同舟云学术

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Thermodynamic database on U-Pu-Zr-Np-Am-Fe alloy system II — Evaluation of Np, Am, and Fe containing systems-

Published:2010-03-01 Issue: Volume:9 Page:012023
ISSN:1757-899X
Container-title:IOP Conference Series: Materials Science and Engineering
language:
Short-container-title:IOP Conf. Ser.: Mater. Sci. Eng.

Author:

Kurata M

Publisher

IOP Publishing

Subject

General Medicine

Link

http://stacks.iop.org/1757-899X/9/i=1/a=012023/pdf

Reference26 articles.

1. Fuel/cladding compatibility in U-19Pu-10Zr/HT9-clad fuel at elevated temperatures

2. Interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys

3. Thermodynamic assessment of the Fe–U, U–Zr and Fe–U–Zr systems

Cited by 19 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. Thermodynamic analysis for molten corium stratification with U-Zr-O-Fe database;Journal of Nuclear Materials;2023-02

2. Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel;Journal of Nuclear Materials;2022-12

3. TAF-ID: An international thermodynamic database for nuclear fuels applications;Calphad;2021-03

4. Phase Diagram of Corium Systems;Comprehensive Nuclear Materials;2020

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

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