A Statistical Fuel Swelling and Fission Gas Release Model-Reference-Cited by-同舟云学术

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A Statistical Fuel Swelling and Fission Gas Release Model

Published:1970-08 Issue:2 Volume:9 Page:148-166
ISSN:0550-3043
Container-title:Nuclear Applications and Technology
language:en
Short-container-title:Nuclear Applications and Technology

Author:

Warner H. R.¹,Nichols F. A.¹

Affiliation:

1. Fuel Element Development Department, Bettis Atomic Power Laboratory P.O. Box 79, West Mifflin, Pennsylvania 15122

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT70-A28805

Reference32 articles.

1. Xenon diffusion in UO2

Cited by 25 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. Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon;Nuclear Engineering and Technology;2020-12

2. Simulation of high-temperature swelling of uranium dioxide and deformation behavior of a fuel element;Atomic Energy;2007-09

3. On the nuclear oxide fuel densification, swelling and thermal re-sintering;Journal of Nuclear Materials;2002-04

4. On the behaviour of intragranular fission gas in UO2 fuel;Journal of Nuclear Materials;2000-06

5. Investigation of the gas permeability of porous uranium dioxide;Atomic Energy;1993-05

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