High-uranium-loaded U/sub 3/O/sub 8/--Al Fuel Element Development Program PDF Download

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High-uranium-loaded U/sub 3/O/sub 8/--Al Fuel Element Development Program

High-uranium-loaded U/sub 3/O/sub 8/--Al Fuel Element Development Program PDF 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

High-uranium-loaded U/sub 3/O/sub 8/--Al Fuel Element Development Program PDF 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.

Fabrication of High-uranium-loaded U[sub]3[/sub]O[sub]8[/sub]-Al Developmental Fuel Plates

Fabrication of High-uranium-loaded U[sub]3[/sub]O[sub]8[/sub]-Al Developmental Fuel Plates PDF 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.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1550

Book Description


Energy Research Abstracts

Energy Research Abstracts PDF 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.

Proceedings of Technical Meetings

Proceedings of Technical Meetings PDF Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 62

Book Description


Government Reports Announcements & Index

Government Reports Announcements & Index PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 1288

Book Description


Government Reports Annual Index

Government Reports Annual Index PDF Author:
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 882

Book Description


TID.

TID. PDF Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 212

Book Description


Indexed Bibliography of Current Nuclear Safety Literature

Indexed Bibliography of Current Nuclear Safety Literature PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 128

Book Description


Progress Report

Progress Report PDF Author: Instituto de Pesquisas Energéticas e Nucleares (Brazil)
Publisher:
ISBN:
Category : Nuclear chemistry
Languages : en
Pages : 262

Book Description