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Technical specification: Mixed-oxide pellets for the light-water reactor irradiation demonstration test

Description: This technical specification is a Level 2 Document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-oxide Fuel Irradiation Test Project Plan. It is patterned after the pellet specification that was prepared by Atomic Energy of Canada, Limited, for use by Los Alamos National Laboratory in fabrication of the test fuel for the Parallex Project, adjusted as necessary to reflect the differences between the Canadian uranium-deuterium reactor and light-water reactor fu… more
Date: June 1997
Creator: Cowell, B. S.
Partner: UNT Libraries Government Documents Department
open access

Incentives and techniques for increasing the capacity of the geologic repository

Description: Estimates of the materials potentially destined for emplacement in Yucca Mountain exceed the statutory repository capacity limit of 70,000 metric tons initial heavy metal. Removal and subsequent burning of the actinides in these materials can dramatically increase the repository capacity, postponing or perhaps eliminating the need for a second repository. The detailed calculations described herein verify portions of a promising actinide removal and waste emplacement concept, HEWEC. Results from… more
Date: September 1, 1994
Creator: Cowell, B. S.; Fontana, M. H. & Michaels, G. E.
Partner: UNT Libraries Government Documents Department
open access

Survey of Worldwide Light Water Reactor Experience with Mixed Uranium-Plutonium Oxide Fuel

Description: The US and the Former Soviet Union (FSU) have recently declared quantities of weapons materials, including weapons-grade (WG) plutonium, excess to strategic requirements. One of the leading candidates for the disposition of excess WG plutonium is irradiation in light water reactors (LWRs) as mixed uranium-plutonium oxide (MOX) fuel. A description of the MOX fuel fabrication techniques in worldwide use is presented. A comprehensive examination of the domestic MOX experience in US reactors obtain… more
Date: February 1, 1999
Creator: Cowell, B. S. & Fisher, S. E.
Partner: UNT Libraries Government Documents Department
open access

Fuel qualification issues and strategies for reactor-based surplus plutonium disposition

Description: The Department of Energy (DOE) has proposed irradiation of mixed-oxide (MOX) fuel in existing commercial reactors as a disposition method for surplus plutonium from the weapons program. The burning of MOX fuel in reactors is supported by an extensive technology base; however, the infrastructure required to implement reactor-based plutonium disposition does not exist domestically. This report identifies and examines the actions required to qualify and license weapons-grade (WG) plutonium-based M… more
Date: August 1, 1997
Creator: Cowell, B. S.; Copeland, G. L. & Moses, D. L.
Partner: UNT Libraries Government Documents Department
open access

Light water reactor mixed-oxide fuel irradiation experiment

Description: The United States Department of Energy Office of Fissile Materials Disposition is sponsoring and Oak Ridge National Laboratory (ORNL) is leading an irradiation experiment to test mixed uranium-plutonium oxide (MOX) fuel made from weapons-grade (WG) plutonium. In this multiyear program, sealed capsules containing MOX fuel pellets fabricated at Los Alamos National Laboratory (LANL) are being irradiated in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laborato… more
Date: June 1, 1998
Creator: Hodge, S.A.; Cowell, B.S.; Chang, G.S. & Ryskamp, J.M.
Partner: UNT Libraries Government Documents Department
open access

Accelerator-based conversion (ABC) of weapons plutonium: Plant layout study and related design issues

Description: In preparation for and in support of a detailed R and D Plan for the Accelerator-Based Conversion (ABC) of weapons plutonium, an ABC Plant Layout Study was conducted at the level of a pre-conceptual engineering design. The plant layout is based on an adaptation of the Molten-Salt Breeder Reactor (MSBR) detailed conceptual design that was completed in the early 1070s. Although the ABC Plant Layout Study included the Accelerator Equipment as an essential element, the engineering assessment focuse… more
Date: April 1995
Creator: Cowell, B. S.; Fontana, M. H.; Krakowski, R. A.; Beard, C. A.; Buksa, J.J.; Davidson, J. W. et al.
Partner: UNT Libraries Government Documents Department
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