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Oxide fuel transients

Published:1989-07 Issue:1-2 Volume:166 Page:165-178
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Matzke Hj.,Blank H.,Coquerelle M.,Lassmann K.,Ray I.L.F.,Ronchi C.,Walker C.T.

Publisher

Elsevier BV

Subject

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

Reference34 articles.

1. Local fission gas release and swelling in water reactor fuel during slow power transients

2. Fuel Rod Internal Chemistry and Fission Product Behaviour;Mogensen,1986

3. Proc. Jahrestagung Kerntechnik;Blank,1988

4. Measurement of retained xenon in advanced fuels by microprobe analysis

Cited by 68 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. Thermal Energy Transport in Oxide Nuclear Fuel;Chemical Reviews;2021-12-17

2. The formation mechanisms of high burnup structure in UO2 fuel;Journal of Nuclear Materials;2021-12

3. An Atomic-Scale Understanding of UO2 Surface Evolution during Anoxic Dissolution;ACS Applied Materials & Interfaces;2020-08-10

4. Lattice strain mapping of cracks and indentations in UO2 using synchrotron microdiffraction;Journal of Nuclear Materials;2020-02

5. Radiation Effects in UO2;Comprehensive Nuclear Materials;2020

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