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U.S. Department of Energy
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Review of radiation shielding concerns associated with the TMI-2 (Three Mile Island Unit 2) defueling system

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5831418

The defueling system for TMI-2 was designed with maximum versatility and broad functional requirements to remove the damaged core from the reactor vessel. This was done without the ability to precisely define the operations or even the conditions of the core debris. The approach used in the design of the defueling system required planning to minimize critical path defueling time and to minimize time and worker exposure for installation and maintenance. Provisions were made to maximize pre-installed equipment assembly and checkout, to provide versatile equipment and tooling, and to achieve low maintenance on the defueling equipment and tooling. These provisions are also examples of how the as-low-as-reasonably-achievable (ALARA) principle was implemented during the design phase of the TMI-2 defueling program. During the defueling operations, it has been demonstrated that the implemented shielding requirements have provided excellent protection of operators and other workers in the reactor building. Collective exposures of the defueling operators have been maintained low, and no overexposure due to handling fuel canisters has occurred.

Research Organization:
Bechtel, Gaithersburg, MD (USA)
OSTI ID:
5831418
Report Number(s):
CONF-881011-
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 57; ISSN TANSA
Country of Publication:
United States
Language:
English