TMI-2 transportation program - Design considerations for the NUPAC 125-B cask handling and loading/unloading equipment
Conference
·
· Nucl. Mater. Manage. Annu. Meet. Proc.; (United States)
OSTI ID:5817760
Removal, transport and receipt of core debris from the damaged reactor at Three Mile Island Unit 2 (TMI-2) required the design of transport cask handling and ''dry'' loading and unloading equipment. The system for ''dry'' (not underwater) loading of the transport cask includes; 1) equipment for handling the cask, 2) equipment for loading core debris canisters into the cask at TMI, and 3) equipment for removing the canisters in a hot cell facility. This paper reviews the technical design considerations operational parameters and summarizes lessons learned in the design, testing, startup and use of the equipment provided for the TMI-2 Transportation Program.
- Research Organization:
- Nuclear Packaging, Inc., Federal Way, WA
- OSTI ID:
- 5817760
- Report Number(s):
- CONF-870713-
- Conference Information:
- Journal Name: Nucl. Mater. Manage. Annu. Meet. Proc.; (United States) Journal Volume: 16
- Country of Publication:
- United States
- Language:
- English
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