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086 0 |a E 1.99:827384 
086 0 |a E 1.99:827384 
245 0 0 |a Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility  |h [electronic resource] 
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 2003. 
300 |a 8 pages :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through the Information Bridge: DOE Scientific and Technical Information. 
500 |a 02/25/2003. 
500 |a Waste Management 2003 Symposium, Tucson, AZ (US), 02/23/2003--02/27/2003. 
500 |a Dippre, M. A. 
500 |a Foster Wheeler Environmental Corporation, Richland, WA (US) 
520 3 |a A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational time savings, and significantly improved ALARA exposure. 
650 7 |a Design.  |2 local. 
650 7 |a Nuclear Fuels.  |2 local. 
650 7 |a Shielding.  |2 local. 
650 7 |a Waste Processing.  |2 local. 
650 7 |a Containers.  |2 local. 
650 7 |a Light Bulbs.  |2 local. 
650 7 |a Spent Fuels.  |2 local. 
650 7 |a Monitoring.  |2 local. 
650 7 |a Wastes.  |2 local. 
650 7 |a Processing.  |2 local. 
650 7 |a Waste Management.  |2 local. 
650 7 |a Machinery.  |2 local. 
650 7 |a Solid Wastes.  |2 local. 
650 7 |a Contact Handling.  |2 local. 
650 7 |a Nuclear Fuel Cycle And Fuel Materials.  |2 edbsc. 
650 7 |a Management Of Radioactive Wastes, And Non-radioactive Wastes From Nuclear Facilities.  |2 edbsc. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
856 4 0 |u http://www.osti.gov/servlets/purl/827384-69A55T/native/  |z Online Access 
907 |a .b69972540  |b 03-06-23  |c 03-31-12 
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952 f f |p Can circulate  |a University of Colorado Boulder  |b Online  |c Online  |d Online  |e E 1.99:827384  |h Superintendent of Documents classification  |i web  |n 1