Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An experiment to evaluate the irradiation characteristics of various candidate low-enriched, high-uranium content fuels for research and test reactors was performed for the US Department of Energy Reduced Enrichment Research and Test Reactor Program. The experiment included the irradiation of 244 miniature fuel plates (miniplates) in a core position in the Oak Ridge Research Reactor. The miniplates were aluminum-based, dispersion-type plates 114.3 mm long by 50.8 mm wide with overall plate thicknesses of 1.27 or 1.52 mm. Fuel core dimensions varied according to the overall plate thicknesses with a minimum clad thickness of 0.20 mm. Tested fuels included UAl(subscript x), UAl2, U3O, U3SiAl, U3Si, U3Si/sub 1.5/, U3Si2, U3SiCu, USi, U6Fe, and U6Mn/sub 1.3/ materials. Although most miniplates were made with low-enriched uranium (19.9%), some with medium-enriched uranium (40 to 45%), a few with high-enriched uranium (93%), and a few with depleted uranium (0.2 to 0.4%) were tested for comparison. These fuel materials were irradiated to burnups ranging from (approximately)27 to 98 at. % 235U depletion. Operation of the experiment, measurement of miniplate thickness as the irradiation progressed, ultimate shipment of the irradiated miniplates to various hot cells, and preliminary results are reported here. 18 refs., 12 figs., 7 tabs.
Summary Report on the HFED (High-Uranium-Loaded Fuel Element Development) Miniplate Irradiations for the RERTR (Reduced Enrichment Research and Test Reactor) Program
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An experiment to evaluate the irradiation characteristics of various candidate low-enriched, high-uranium content fuels for research and test reactors was performed for the US Department of Energy Reduced Enrichment Research and Test Reactor Program. The experiment included the irradiation of 244 miniature fuel plates (miniplates) in a core position in the Oak Ridge Research Reactor. The miniplates were aluminum-based, dispersion-type plates 114.3 mm long by 50.8 mm wide with overall plate thicknesses of 1.27 or 1.52 mm. Fuel core dimensions varied according to the overall plate thicknesses with a minimum clad thickness of 0.20 mm. Tested fuels included UAl(subscript x), UAl2, U3O, U3SiAl, U3Si, U3Si/sub 1.5/, U3Si2, U3SiCu, USi, U6Fe, and U6Mn/sub 1.3/ materials. Although most miniplates were made with low-enriched uranium (19.9%), some with medium-enriched uranium (40 to 45%), a few with high-enriched uranium (93%), and a few with depleted uranium (0.2 to 0.4%) were tested for comparison. These fuel materials were irradiated to burnups ranging from (approximately)27 to 98 at. % 235U depletion. Operation of the experiment, measurement of miniplate thickness as the irradiation progressed, ultimate shipment of the irradiated miniplates to various hot cells, and preliminary results are reported here. 18 refs., 12 figs., 7 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An experiment to evaluate the irradiation characteristics of various candidate low-enriched, high-uranium content fuels for research and test reactors was performed for the US Department of Energy Reduced Enrichment Research and Test Reactor Program. The experiment included the irradiation of 244 miniature fuel plates (miniplates) in a core position in the Oak Ridge Research Reactor. The miniplates were aluminum-based, dispersion-type plates 114.3 mm long by 50.8 mm wide with overall plate thicknesses of 1.27 or 1.52 mm. Fuel core dimensions varied according to the overall plate thicknesses with a minimum clad thickness of 0.20 mm. Tested fuels included UAl(subscript x), UAl2, U3O, U3SiAl, U3Si, U3Si/sub 1.5/, U3Si2, U3SiCu, USi, U6Fe, and U6Mn/sub 1.3/ materials. Although most miniplates were made with low-enriched uranium (19.9%), some with medium-enriched uranium (40 to 45%), a few with high-enriched uranium (93%), and a few with depleted uranium (0.2 to 0.4%) were tested for comparison. These fuel materials were irradiated to burnups ranging from (approximately)27 to 98 at. % 235U depletion. Operation of the experiment, measurement of miniplate thickness as the irradiation progressed, ultimate shipment of the irradiated miniplates to various hot cells, and preliminary results are reported here. 18 refs., 12 figs., 7 tabs.
Energy Research Abstracts
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.
ERDA Energy Research Abstracts
Nuclear Regulatory Commission Issuances
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950
Book Description
Proceedings of the ... International Conference on Nuclear Engineering
Government Reports Annual Index
Author:
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 1364
Book Description
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 1364
Book Description
Government Reports Announcements & Index
Development of Very High-density Low-enriched Uranium Fuels
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
The RERTR program has recently begun an aggressive effort to develop dispersion fuels for research and test reactors with uranium densities of 8 to 9 g U/cm3, based on the use of [gamma]-stabilized uranium alloys. Fabrication development teams and facilities are being put into place and preparations for the first irradiation test are in progress. The first screening irradiations are expected to begin in late April 1997 and first results should be available by end of 1997. Discussions with potential international partners in fabrication development and irradiation testing have begun.
Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
The RERTR program has recently begun an aggressive effort to develop dispersion fuels for research and test reactors with uranium densities of 8 to 9 g U/cm3, based on the use of [gamma]-stabilized uranium alloys. Fabrication development teams and facilities are being put into place and preparations for the first irradiation test are in progress. The first screening irradiations are expected to begin in late April 1997 and first results should be available by end of 1997. Discussions with potential international partners in fabrication development and irradiation testing have begun.
Fuel Element Development Program for the Pebble Bed Reactor
Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 164
Book Description
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 164
Book Description