Simulation of uranium mononitride spent fuel: A thermodynamic approach-Reference-Cited by-同舟云学术

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Simulation of uranium mononitride spent fuel: A thermodynamic approach

Published:2024-04 Issue: Volume:592 Page:154900
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Degueldre Claude,Goddard Dave,Berhane Ghebrehiwot,Simpson Allan,Boxall Colin

Funder

Department for Business, Energy and Industrial Strategy, UK Government

Lancaster University

Publisher

Elsevier BV

Reference93 articles.

1. The Analysis of Nuclear Materials and Their Environments;Degueldre,2017

2. Plutonium–uranium mixed oxide characterization by coupling micro-X-ray diffraction and absorption investigations;Degueldre;J. Nuclear Mater.,2011

3. Post irradiation examination of nuclear fuel: toward a complete analysis;Degueldre;Progress Nuclear Energy,2016

4. Redox state of plutonium in irradiated mixed oxide fuels;Degueldre;J. Phys. Chem. Solids,2014

5. Fission product speciation across a UO2 spent nuclear fuel;Klosek;J. Nuclear Mater.,2023

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. Evaluation on Thermodynamic Compatibility between High Density Ceramic Nuclear Reactor Fuels Ux(X=C,N) and Light Water Reactor Cladding Materials (Zr and Sic);2024

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