Separation processes for high-level radioactive waste treatment [electronic resource]

During World War II, production of nuclear materials in the United States for national defense, high-level waste (HLW) was generated as a byproduct. Since that time, further quantities of HLW radionuclides have been generated by continued nuclear materials production, research, and the commercial nu...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Westinghouse Hanford Company (Researcher), United States. Department of Energy. Richland Operations Office (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1992.
Subjects:

MARC

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260 |a Washington, D.C. :  |b United States. Dept. of Energy ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1992. 
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500 |a Engineering Foundation conference on dispersion and aggregation,Palm Coast, FL (United States),15-20 Mar 1992. 
500 |a Sutherland, D.G. 
513 |a Quarterly;  |b 07/01/1992 - 09/30/1992. 
520 3 |a During World War II, production of nuclear materials in the United States for national defense, high-level waste (HLW) was generated as a byproduct. Since that time, further quantities of HLW radionuclides have been generated by continued nuclear materials production, research, and the commercial nuclear power program. In this paper HLW is defined as the highly radioactive material resulting from the processing of spent nuclear fuel. The HLW is the liquid waste generated during the recovery of uranium and plutonium in a fuel processing plant that generally contains more than 99% of the nonvolatile fission products produced during reactor operation. Since this paper deals with waste separation processes, spent reactor fuel elements that have not been dissolved and further processed are excluded. 
536 |b AC06-87RL10930. 
650 7 |a Tanks.  |2 local. 
650 7 |a Organic Compounds.  |2 local. 
650 7 |a Grouting.  |2 local. 
650 7 |a Ferrocyanides.  |2 local. 
650 7 |a Separation Processes.  |2 local. 
650 7 |a Containers.  |2 local. 
650 7 |a Vitrification.  |2 local. 
650 7 |a Hanford Reservation.  |2 local. 
650 7 |a Cesium 137.  |2 local. 
650 7 |a High-level Radioactive Wastes.  |2 local. 
650 7 |a Radioactive Waste Processing.  |2 local. 
650 7 |a Sludges.  |2 local. 
650 7 |a Inventories.  |2 local. 
650 7 |a Strontium 90.  |2 local. 
650 7 |a Salts.  |2 local. 
650 7 |a Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities.  |2 edbsc. 
710 2 |a Westinghouse Hanford Company.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Richland Operations Office.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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