A preliminary evaluation of the ability of from-reactor casks to geometrically accommodate commercial LWR spent nuclear fuel

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:6043199

Andress, D ^[1]; Joy, D S ^[2]; McLeod, N B ^[3]; Peterson, R W ^[4]; Rahimi, M ^[5]

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1. Andress (David) and Associates, Inc., Kensington, MD (USA)
2. Oak Ridge National Lab., TN (USA)
3. Johnson (E.R.) Associates, Inc., Oakton, VA (USA)
4. Bentz (E.J.) and Associates, Inc., Alexandria, VA (USA)
5. Jacobs Engineering Group, Inc., Washington, DC (USA)

The Department of Energy has sponsored a number of cask design efforts to define several transportation casks to accommodate the various assemblies expected to be accepted by the Federal Waste Management System. At this time, three preliminary cask designs have been selected for the final design--the GA-4 and GA-9 truck casks and the BR-100 rail cask. In total, this assessment indicates that the current Initiative I cask designs can be expected to dimensionally accommodate 100% of the PWR fuel assemblies (other than the extra-long South Texas Fuel) with control elements removed, and >90% of the assemblies having the control elements as an integral part of the fuel assembly. For BWR assemblies, >99% of the assemblies can be accommodated with fuel channels removed. This paper summarizes preliminary results of one part of that evaluation related to the ability of the From-Reactor Initiative I casks to accommodate the physical and radiological characteristics of the Spent Nuclear Fuel projected to be accepted into the Federal Waste Management System. 3 refs., 5 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: DOE/RW
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6043199
• Report Number(s): CONF-910435-17; ON: DE91005481; TRN: 91-004653
• Resource Relation: Conference: American Nuclear Society (ANS) international high level radioactive waste management conference, Las Vegas, NV (USA), 28 Apr - 3 May 1991
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CASKS
SPECIFICATIONS
SPENT FUELS
TRANSPORT
DESIGN
WATER COOLED REACTORS
CONTAINERS
ENERGY SOURCES
FUELS
MATERIALS
NUCLEAR FUELS
REACTOR MATERIALS
REACTORS
420204* - Engineering- Shipping Containers
050900 - Nuclear Fuels- Transport
Handling
& Storage