The impact of using reduced capacity baskets on cask fleet size and cask fleet mix [electronic resource]

The Civilian Radioactive Waste Management System transportation system will encounter a wide range of spent fuel characteristics. Since the Initiative I casks are being designed to transport 10-year-old fuel with a burnup of 35,000 MWd/MTU, there is a good likelihood that a number of the cask shipme...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Oak Ridge National Laboratory (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, 1993.
Subjects:

MARC

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245 0 4 |a The impact of using reduced capacity baskets on cask fleet size and cask fleet mix  |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 1993. 
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500 |a 10. international high-level radioactive waste management conference,Las Vegas, NV (United States),25-29 Apr 1993. 
500 |a Johnson, P.E.; Joy, D.S.; Andress, D.A. 
520 3 |a The Civilian Radioactive Waste Management System transportation system will encounter a wide range of spent fuel characteristics. Since the Initiative I casks are being designed to transport 10-year-old fuel with a burnup of 35,000 MWd/MTU, there is a good likelihood that a number of the cask shipments will need to be derated in order to meet the Nuclear Regulatory Commission radiation guidelines. This report discusses the impact of cask derating by using reduced-capacity baskets. Cask derating, while enhancing the ability to move spent fuel with a wider range of age and burnup characteristics, increases the number of shipments; the amount of equipment (cask bodies, baskets, etc.); and the number of visits to both shipping and receiving sites required to transport a specific amount of spent fuel. 
536 |b AC05-84OR21400. 
650 7 |a Radioactive Waste Management.  |2 local. 
650 7 |a Spent Fuel Casks.  |2 local. 
650 7 |a Capacity.  |2 local. 
650 7 |a Bwr Type Reactors.  |2 local. 
650 7 |a Monitored Retrievable Storage.  |2 local. 
650 7 |a Pwr Type Reactors.  |2 local. 
650 7 |a Evaluation.  |2 local. 
650 7 |a Nuclear Waste Policy Acts.  |2 local. 
650 7 |a Radioactive Wastes.  |2 local. 
650 7 |a Waste Transportation.  |2 local. 
650 7 |a Materials Handling.  |2 local. 
650 7 |a Nuclear Fuel Cycle And Fuel Materials.  |2 edbsc. 
710 2 |a Oak Ridge National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
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