Spent Nuclear Fuel Dry Transfer System Cold Demonstration Project Final Report [electronic resource].
- Published:
- Washington, D.C. : United States. Dept. of Energy, 1999.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Additional Creators:
- Idaho National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- The spent nuclear fuel dry transfer system (DTS) provides an interface between large and small casks and between storage-only and transportation casks. It permits decommissioning of reactor pools after shutdown and allows the use of large storage-only casks for temporary onsite storage of spent nuclear fuel irrespective of reactor or fuel handling limitations at a reactor site. A cold demonstration of the DTS prototype was initiated in August 1996 at the Idaho National Engineering and Environmental Laboratory (INEEL). The major components demonstrated included the fuel assembly handling subsystem, the shield plug/lid handling subsystem, the cask interface subsystem, the demonstration control subsystem, a support frame, and a closed circuit television and lighting system. The demonstration included a complete series of DTS operations from source cask receipt and opening through fuel transfer and closure of the receiving cask. The demonstration included both normal operations and recovery from off-normal events. It was designed to challenge the system to determine whether there were any activities that could be made to jeopardize the activities of another function or its safety. All known interlocks were challenged. The equipment ran smoothly and functioned as designed. A few "bugs" were corrected. Prior to completion of the demonstration testing, a number of DTS prototype systems were modified to apply lessons learned to date. Additional testing was performed to validate the modifications. In general, all the equipment worked exceptionally well. The demonstration also helped confirm cost estimates that had been made at several points in the development of the system.
- Report Numbers:
- E 1.99:ineel/ext-99-01335
ineel/ext-99-01335 - Subject(s):
- Other Subject(s):
- Casks
- Closures
- Decommissioning
- Ineel
- Interlocks
- Lighting Systems
- Modifications
- Nuclear Fuels
- Openings
- Reactor Sites
- Safety
- Shields
- Shutdown
- Storage
- Testing
- Spent Fuels
- Cask Interface
- Casks
- Cold Demonstration
- Dry Transfer System
- Fuel Assembly Handling
- Fuel Transfer
- Off-Normal Events
- Shield Plug/Lid Handling
- Spent Nuclear Fuel
- Note:
- Published through SciTech Connect.
12/01/1999.
"ineel/ext-99-01335"
McKinnon, M. A.; Christensen, Max R. - Funding Information:
- DE-AC07-99ID-13727
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