Experience with failed or damaged spent fuel and its impacts on handling [electronic resource]

Spent fuel management planning needs to include consideration of failed or damaged spent light-water reactor (LWR) fuel. Described in this paper, which was prepared under the Commercial Spent Fuel Management (CSFM) Program that is sponsored by the US Department of Energy (DOE), are the following: th...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Las Vegas, Nev. : Oak Ridge, Tenn. : United States. Dept. of Energy. Office of Civilian Radioactive Waste Management ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1989.
Subjects:

MARC

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245 0 0 |a Experience with failed or damaged spent fuel and its impacts on handling  |h [electronic resource] 
260 |a Las Vegas, Nev. :  |b United States. Dept. of Energy. Office of Civilian Radioactive Waste Management ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1989. 
300 |a Pages: (8 p) :  |b digital, PDF file. 
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500 |a 12/01/1989. 
500 |a "pnl-sa-17727" 
500 |a " conf-900161--5" 
500 |a "DE90008614" 
500 |a 7. Institute of Nuclear Materials Management spent fuel management seminar, Washington, DC (USA), 17-19 Jan 1990. 
500 |a Bailey, W.J. 
520 3 |a Spent fuel management planning needs to include consideration of failed or damaged spent light-water reactor (LWR) fuel. Described in this paper, which was prepared under the Commercial Spent Fuel Management (CSFM) Program that is sponsored by the US Department of Energy (DOE), are the following: the importance of fuel integrity and the behavior of failed fuel, the quantity and burnup of failed or damaged fuel in storage, types of defects, difficulties in evaluating data on failed or damaged fuel, experience with wet storage, experience with dry storage, handling of failed or damaged fuel, transporting of fuel, experience with higher burnup fuel, and conclusions. 15 refs. 
536 |b AC06-76RL01830. 
650 7 |a Safety.  |2 local. 
650 7 |a Water Moderated Reactors.  |2 local. 
650 7 |a Reactor Safety.  |2 local. 
650 7 |a Damage.  |2 local. 
650 7 |a Waste Transportation.  |2 local. 
650 7 |a Recommendations.  |2 local. 
650 7 |a Fuel Element Failure.  |2 local. 
650 7 |a Fuel Elements.  |2 local. 
650 7 |a Technology Assessment.  |2 local. 
650 7 |a Spent Fuel Elements.  |2 local. 
650 7 |a Reactor Accidents.  |2 local. 
650 7 |a Management.  |2 local. 
650 7 |a Storage.  |2 local. 
650 7 |a Systems Analysis.  |2 local. 
650 7 |a Water Cooled Reactors.  |2 local. 
650 7 |a Bwr Type Reactors.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Materials Handling.  |2 local. 
650 7 |a Burnup.  |2 local. 
650 7 |a Radioactive Waste Storage.  |2 local. 
650 7 |a Failure Mode Analysis.  |2 local. 
650 7 |a Risk Assessment.  |2 local. 
650 7 |a Waste Storage.  |2 local. 
650 7 |a Waste Management.  |2 local. 
650 7 |a Transport.  |2 local. 
650 7 |a System Failure Analysis.  |2 local. 
650 7 |a Fuel Cans.  |2 local. 
650 7 |a Fuel Management.  |2 local. 
650 7 |a Pwr Type Reactors.  |2 local. 
650 7 |a Reactor Components.  |2 local. 
650 7 |a Defects.  |2 local. 
650 7 |a Accidents.  |2 local. 
650 7 |a Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities.  |2 edbsc. 
650 7 |a Nuclear Fuel Cycle And Fuel Materials.  |2 edbsc. 
650 7 |a General Studies Of Nuclear Reactors.  |2 edbsc. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
710 2 |a Pacific Northwest Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Civilian Radioactive Waste Management.  |4 spn. 
710 2 |a Pacific Northwest National Laboratory (U.S.).  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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