Thermophysical and thermochemical properties of U-23wt.%Pu-6wt.%Zr alloy fuel: Computational and high temperature mass spectrometric studies-Reference-Cited by-同舟云学术

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Thermophysical and thermochemical properties of U-23wt.%Pu-6wt.%Zr alloy fuel: Computational and high temperature mass spectrometric studies

Published:2020-10 Issue: Volume:539 Page:152251
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Trinadh V.V.,Manikandan P.,Bera Suranjan,Ghosh Suddhasattwa,Brahmananda Rao C.V.S.,Lakshmi Narasimhan T.S.,Joseph M.

Publisher

Elsevier BV

Subject

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

Reference27 articles.

1. Studies on physics parameters of metal (U-Pu-Zr) fuelled FBR cores;Riyas;Ann. Nucl. Energy,2008

2. Metallic fast reactor fuels;Hofman;Prog. Nucl. Energy,1997

3. High Temperature Chemistry of Molybdenum, Cesium, Iodine and UO2+x;McFarlane,1996

4. A critical review of the experimentally known properties of U-Pu-Zr alloys, Part 1: phases and phase diagrams;Janney;Nucl. Technol.,2019

Cited by 3 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. Knudsen effusion mass spectrometry: Current and future approaches;Rapid Communications in Mass Spectrometry;2024-05-14

2. TEM-based phase characterization of U–19Pu–10Zr irradiated in ATR;MRS Bulletin;2022-11-02

3. Recent trends in metallic fast reactor fuels research;Journal of Nuclear Materials;2022-01

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