Performance of oxide nuclear fuel in water-cooled power reactors-Reference-Cited by-同舟云学术

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Performance of oxide nuclear fuel in water-cooled power reactors

Published:1988-04 Issue: Volume:153 Page:3-15
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Stehle H.

Publisher

Elsevier BV

Subject

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

Reference6 articles.

1. Irradiation-induced densification of UO2 pellet fuel

2. Proc. IAEA Technical Committee, Meeting on Fuel Rod Internal Chemistry and Fission Product Behaviour;Sontheimer,1986

Cited by 26 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. Study on the relationship between fuel fragmentation during a LOCA and pellet microstructure;Journal of Nuclear Science and Technology;2021-06-30

2. Determination of the pressure in micrometric bubbles in irradiated nuclear fuels;Journal of Nuclear Materials;2021-01

3. Unified Effect of Dispersed Xe on the Thermal Conductivity of UO2 Predicted by Three Interatomic Potentials;JOM;2020-01-08

4. Fuel Performance of Light Water Reactors (Uranium Oxide and MOX);Comprehensive Nuclear Materials;2020

5. Engineering Design of a Mechanical Decladder for Spent Nuclear Rod-Cuts;Science and Technology of Nuclear Installations;2019-08-14

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