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Author:
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Category : Uranium
Languages : en
Pages : 24
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Book Description
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.
Author:
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 24
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Book Description
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.
Author: J. L. Bates
Publisher:
ISBN:
Category : Mixed oxide fuels (Nuclear engineering)
Languages : en
Pages : 56
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Author: Donald L. Keller
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 28
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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).
Author:
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Category : Nuclear energy
Languages : en
Pages : 1052
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Author:
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Category : Aeronautics
Languages : en
Pages : 358
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Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Author:
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ISBN:
Category : Energy development
Languages : en
Pages : 720
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Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 604
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Author:
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ISBN:
Category : Power resources
Languages : en
Pages : 564
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Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Author:
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Category :
Languages : en
Pages : 90
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Book Description
Author: J. Belle
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 146
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Book Description
