Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The High-Uranium-Loaded U/sub 3/O/sub 8/--Al Fuel Development Program supports Argonne National Laboratory efforts to develop high-uranium-density research and test reactor fuel to accommodate use of low-uranium enrichment. The goal is to fuel most research and test reactors with uranium of less than 20% enrichment for the purpose of lowering the potential for diversion of highly-enriched material for nonpeaceful usages.
High-uranium-loaded U/sub 3/O/sub 8/--Al Fuel Element Development Program
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The High-Uranium-Loaded U/sub 3/O/sub 8/--Al Fuel Development Program supports Argonne National Laboratory efforts to develop high-uranium-density research and test reactor fuel to accommodate use of low-uranium enrichment. The goal is to fuel most research and test reactors with uranium of less than 20% enrichment for the purpose of lowering the potential for diversion of highly-enriched material for nonpeaceful usages.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The High-Uranium-Loaded U/sub 3/O/sub 8/--Al Fuel Development Program supports Argonne National Laboratory efforts to develop high-uranium-density research and test reactor fuel to accommodate use of low-uranium enrichment. The goal is to fuel most research and test reactors with uranium of less than 20% enrichment for the purpose of lowering the potential for diversion of highly-enriched material for nonpeaceful usages.
Fabrication of High-uranium-loaded U[sub]3[/sub]O[sub]8[/sub]-Al Developmental Fuel Plates
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A common plate-type fuel for research and test reactors is U/sub 3/O/sub 8/ dispersed in aluminum and clad with an aluminum alloy. There is an impetus to reduce the /sup 235/U enrichment from above 90% to below 20% for these fuels to lessen the risk of diversion of the uranium for nonpeaceful uses. Thus, the uranium content of the fuel plates has to be increased to maintain the performance of the reactors. This paper describes work at ORNL to determine the maximal uranium loading for these fuels that can be fabricated with commercially proven materials and techniques and that can be expected to perform satisfactorily in service.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A common plate-type fuel for research and test reactors is U/sub 3/O/sub 8/ dispersed in aluminum and clad with an aluminum alloy. There is an impetus to reduce the /sup 235/U enrichment from above 90% to below 20% for these fuels to lessen the risk of diversion of the uranium for nonpeaceful uses. Thus, the uranium content of the fuel plates has to be increased to maintain the performance of the reactors. This paper describes work at ORNL to determine the maximal uranium loading for these fuels that can be fabricated with commercially proven materials and techniques and that can be expected to perform satisfactorily in service.
Nuclear Science Abstracts
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 806
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.
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 806
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.
Proceedings of Technical Meetings
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 62
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 62
Book Description
Government Reports Announcements & Index
Government Reports Annual Index
Author:
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 882
Book Description
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 882
Book Description
TID.
Indexed Bibliography of Current Nuclear Safety Literature
Progress Report
Author: Instituto de Pesquisas Energéticas e Nucleares (Brazil)
Publisher:
ISBN:
Category : Nuclear chemistry
Languages : en
Pages : 262
Book Description
Publisher:
ISBN:
Category : Nuclear chemistry
Languages : en
Pages : 262
Book Description