Estimated source terms for radionuclides and suspended particulates during TMI-2 defueling operations report on Phase I
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 on relevant parameters were reviewed as the first phase of a project to develop estimates of source terms for soluble radionuclides, particulate radionuclides, and total suspended particulates during TMI-2 defueling operations. The approaches to be used in developing these estimates during Phase II are discussed in general terms. Additional measurements that could improve the quality of the estimates are recommended.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5558975
- Report Number(s):
- GEND-INF-019; ON: DE82010611; TRN: 82-007870
- Country of Publication:
- United States
- Language:
- English
Similar Records
Ex-Vessel Defueling for TMI-2
TMI-2 (Three Mile Island Unit 2) Ex-Vessel Defueling
Related Subjects
THREE MILE ISLAND-2 REACTOR
ACTIVITY LEVELS
PRIMARY COOLANT CIRCUITS
REACTOR MAINTENANCE
RADIOACTIVITY TRANSPORT
REPAIR
WATER CHEMISTRY
CHEMISTRY
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
MAINTENANCE
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled