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Title: Vitrification of excess plutonium

Abstract

As a result of nuclear disarmament activities, many thousands of nuclear weapons are being retired in the US and Russia, producing a surplus of about 50 MT of weapons grade plutonium (Pu) in each country. In addition, the Department of Energy (DOE) has more than 20 MT of Pu scrap, residue, etc., and Russia is also believed to have at least as much of this type of material. The entire surplus Pu inventories in the US and Russia present a clear and immediate danger to national and international security. It is important that a solution be found to secure and manage this material effectively and that such an effort be implemented as quickly as possible. One option under consideration is vitrification of Pu into a relatively safe, durable, accountable, proliferation-resistant form. As a result of decades of experience within the DOE community involving vitrification of a variety of hazardous and radioactive wastes, this existing technology can now be expanded to include immobilization of large amounts of Pu. This technology can then be implemented rapidly using the many existing resources currently available. A strategy to vitrify many different types of Pu will be discussed. In this strategy, the arsenal of vitrificationmore » tools, procedures and techniques already developed throughout the waste management community can be used in a staged Pu vitrification effort. This approach uses the flexible vitrification technology already available and can even be made portable so that it may be brought to the source and ultimately, used to produce a common, borosilicate glass form for the vitrified Pu. The final composition of this product can be made similar to nationally and internationally accepted HLW glasses.« less

Authors:
; ;
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
32594
Report Number(s):
WSRC-MS-94-0486; CONF-950216-63
ON: DE95006452; TRN: 95:008863
DOE Contract Number:  
AC09-89SR18035
Resource Type:
Conference
Resource Relation:
Conference: Waste management `95, Tucson, AZ (United States), 26 Feb - 2 Mar 1995; Other Information: PBD: [1994]
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEFENSE; 35 ARMS CONTROL; NUCLEAR EXPLOSIVES; VITRIFICATION; NUCLEAR WEAPONS; DECOMMISSIONING; RADIOACTIVE WASTE PROCESSING; ARMS CONTROL; SAFEGUARDS

Citation Formats

Wicks, G.G., Mckibben, J.M., and Plodinec, M.J. Vitrification of excess plutonium. United States: N. p., 1994. Web.
Wicks, G.G., Mckibben, J.M., & Plodinec, M.J. Vitrification of excess plutonium. United States.
Wicks, G.G., Mckibben, J.M., and Plodinec, M.J. Sat . "Vitrification of excess plutonium". United States. https://www.osti.gov/servlets/purl/32594.
@article{osti_32594,
title = {Vitrification of excess plutonium},
author = {Wicks, G.G. and Mckibben, J.M. and Plodinec, M.J.},
abstractNote = {As a result of nuclear disarmament activities, many thousands of nuclear weapons are being retired in the US and Russia, producing a surplus of about 50 MT of weapons grade plutonium (Pu) in each country. In addition, the Department of Energy (DOE) has more than 20 MT of Pu scrap, residue, etc., and Russia is also believed to have at least as much of this type of material. The entire surplus Pu inventories in the US and Russia present a clear and immediate danger to national and international security. It is important that a solution be found to secure and manage this material effectively and that such an effort be implemented as quickly as possible. One option under consideration is vitrification of Pu into a relatively safe, durable, accountable, proliferation-resistant form. As a result of decades of experience within the DOE community involving vitrification of a variety of hazardous and radioactive wastes, this existing technology can now be expanded to include immobilization of large amounts of Pu. This technology can then be implemented rapidly using the many existing resources currently available. A strategy to vitrify many different types of Pu will be discussed. In this strategy, the arsenal of vitrification tools, procedures and techniques already developed throughout the waste management community can be used in a staged Pu vitrification effort. This approach uses the flexible vitrification technology already available and can even be made portable so that it may be brought to the source and ultimately, used to produce a common, borosilicate glass form for the vitrified Pu. The final composition of this product can be made similar to nationally and internationally accepted HLW glasses.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1994},
month = {12}
}

Conference:
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