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Irradiation Testing of UO2

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Release : 1960
Genre : Uranium
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Book Synopsis Irradiation Testing of UO2 by :

Download or read book Irradiation Testing of UO2 written by . This book was released on 1960. Available in PDF, EPUB and Kindle. Book excerpt: Included are 167 references to unclassified reports and scientific journals on irradiation testing of unalloyed UO2. Irradiation behavior and effects, heat transfer calculations, fission gas release, post-irradiation examination, and irradiation capsule design are the subject areas covered.

Irradiation Testing of Prototypic UO2-PuO2 PRTR Fuel Elements

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Author :
Release : 1962
Genre :
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Book Synopsis Irradiation Testing of Prototypic UO2-PuO2 PRTR Fuel Elements by : Max D. Freshley

Download or read book Irradiation Testing of Prototypic UO2-PuO2 PRTR Fuel Elements written by Max D. Freshley. This book was released on 1962. Available in PDF, EPUB and Kindle. Book excerpt:

Irradiation Testing of Plutonium-uranium Oxide Nuclear Fuel

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Author :
Release : 1959
Genre : Mixed oxide fuels (Nuclear engineering)
Kind : eBook
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Book Synopsis Irradiation Testing of Plutonium-uranium Oxide Nuclear Fuel by : J. L. Bates

Download or read book Irradiation Testing of Plutonium-uranium Oxide Nuclear Fuel written by J. L. Bates. This book was released on 1959. Available in PDF, EPUB and Kindle. Book excerpt:

Assembly and testing of uo2 specimens for irradiation with a molten core in the x-2 loop

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Author :
Release : 1960
Genre :
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Book Synopsis Assembly and testing of uo2 specimens for irradiation with a molten core in the x-2 loop by : E. Mizzan

Download or read book Assembly and testing of uo2 specimens for irradiation with a molten core in the x-2 loop written by E. Mizzan. This book was released on 1960. Available in PDF, EPUB and Kindle. Book excerpt:

High-temperature Irradiation Test of UO2 Cermet Fuels

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Author :
Release : 1962
Genre : Nuclear fuels
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Book Synopsis High-temperature Irradiation Test of UO2 Cermet Fuels by : Donald L. Keller

Download or read book High-temperature Irradiation Test of UO2 Cermet Fuels written by Donald L. Keller. This book was released on 1962. Available in PDF, EPUB and Kindle. Book excerpt: Niobium-clad niobium cermets and Type 430 stainless steel-clad molybdenum and chromium cermets, all containing 80 vol% 20% enriched UO2, prepared by vapordeposition techniques or from the powders and densified and clad by gas-pressure bonding, were subjected to hightemperature high-heat-flux irradiation in the MTR. Two instrumerted double-walled capsules, each containing duplicate NaK-immersed cylindrical specimens of the three compositions were involved. Specimen diameters were varied according to the particular cermet thermal conductivity in an attempt to secure central temperatures of about 0.6 of the matrix melting point. Probably because of weld failures in both capsules, irradiation temperatures were higher than intended, causing loss of the chromium cermets in one capsule and all of the cermets in the other capsule. The remaining specimens were given a postirradiation dimensional and metallographic examination. The niobium-clad niobium-UO2 cermet exhibited excellent stability at estimated center-line temperatures above 2500 deg F. A density decrease of only 1.4% was measured at a burnup of about 4 at.%. Although the capsule overheating caused the molybdenum-UO2 cermet to partially melt, areas only a few mils from the melted zone showed no evidence of damage from the adverse conditions of the irradiation. (auth).

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