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Nuclear Technology Volume 15, 1972 - Issue 2
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Technical Paper

The Transient Behavior of Vipac and Pellet Thermal Reactor Oxide Fuels

M. D. FreshleyBattelle, Pacific Northwest Laboratories Richland, Washington 99352
&
L. J. HarrisonArgonne National Laboratory, Idaho Facilities Idaho Falls, Idaho 83401
Pages 177-191 | Published online: 12 May 2017

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M. D. Freshley. (1973) UO2-PUO2–A Demonstrated Fuel for Plutonium Utilization in Thermal Reactors. Nuclear Technology 18:2, pages 141-170.
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Articles from other publishers (1)

Makoto Sobajima & Toshio Fujishiro. (1988) Examination of the destructive forces in the chernobyl accident based on NSRR experiments. Nuclear Engineering and Design 106:2, pages 179-190.
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