Estimated source terms for radionuclides and suspended particulates during TMI-2 defueling operations Phase II. Volume II
The selection of methods for removal of the plenum and fuel from the Three Mile Island Unit 2 (TMI-2) reactor vessel will necessarily consider the quantities of radioactivity in solution and associated with suspended particulates in the reactor coolant. The total amount of suspended solids, which affects water clarity and equipment wear, must also be considered in the selection of the defueling technique and the subsystems needed to maintain acceptable operating conditions. Currently available data from TMI-2 and laboratory studies of relevant parameters were reviewed and used to develop estimates of source terms for total suspended particulates, particulate radionuclides, and soluble radionuclides during TMI-2 defueling operations. Potential control techniques for particulates and soluble species were reviewed and their design capabilities were estimated. Additional measurements that could reduce the uncertainty bounds for the estimates are recommended.
- Research Organization:
- Science Applications, Inc., Idaho Falls, ID (USA); Science Applications, Inc., Rockville, MD (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6168205
- Report Number(s):
- GEND-INF-019-Vol.2; ON: DE83011877
- Country of Publication:
- United States
- Language:
- English
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