The Effect of Nuclear Radiation on Dispersion Fuel Materials
The Effect of Nuclear Radiation on Dispersion Fuel Materials

Author: M. Kangilaski

Publisher:

Published: 1966

Total Pages: 80

ISBN-13:

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A complete summary of the irradiation performance of the various fuel materials dispersed in different matrices has been collected. The irradiation performance of the following dispersions is discussed in the report: BeO-UO2, BeO-UO2-ThO2, Al2O3-UO2, MgO-UO2, UO2, UC, UC2, and *U, Th)C2 U3O8 glass, and UAl3 dispersed in aluminum; UO2, UC, and UN dispersed in stainless steel; UO2 and UO2-Y2O3 dispersed in nickel-chromium alloys; UO2 dispersed in niobium, UO2 dispersed in molybdenum, UO2, UN, and UC dispersed in tungsten. The data which is summarized includes percentage of fuel by weight and volume, specimen shape and size, fuel particle size, cladding material and clad thickness, irradiation temperature, heat generation rates, irradiation times, fuel burnup, fission gas release, dimensional and density changes resulting from irradiation. (Author).

Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle
Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle

Author: Jeremy T. Busby

Publisher: Astm International

Published: 2010-01-01

Total Pages: 280

ISBN-13: 9780803134256

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"Fifteen peer-reviewed papers examine radiation damage for the entire fuel cycle. Topics cover: Surveillance programs around the world ; Detailed characterization of irradiated microstructures ; Radiation effects in oxide-dispersion strengthened alloys and austenitic stainless steels ; Modeling helium bubbles ; Finite-element modeling of fuel bundles."--Publisher's website.

Structural Materials for Generation IV Nuclear Reactors
Structural Materials for Generation IV Nuclear Reactors

Author: Pascal Yvon

Publisher: Woodhead Publishing

Published: 2016-08-27

Total Pages: 686

ISBN-13: 0081009127

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Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates Written by an expert in that particular area

Survey of Radiation Effects on Fuel Materials
Survey of Radiation Effects on Fuel Materials

Author: Dwain Bowen

Publisher:

Published: 1957

Total Pages: 86

ISBN-13:

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The changes in properties and dimensions that occur in nuclear fuel materials when fissioning takes place are described. The especially pronounced growth and distortion effects that are observed in uranium are discussed as they are affected by grain size and texture, heat treatment, alloy composition, and mechanical treatment. The characteristics included are gross dimensional change, pimpling, orange peeling, and cracking. The various fundamental considerations or theories that rationalize this behavior are presented. The changes in thermal conductivity, ductility, microstructure, and electrical properties are presented as they apply to all fuels, and these data are used to point out those areas of understanding and those of lack of understanding of the controlling variables in radiation damage to fuels. Some of the problems that require examination and additional data for our future development of high-performance reactor fuel elements are suggested. These include the necessary volume increase occurring at high burnup, the modifications of behavior that may be found when the fuel elements are operated at temperatures above our present experience, and improved mechanical and radiation stability that might be achieved by alloy development or composite design.