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Criticality Analysis Support for the Three Mile Island Unit 2 Fuel Removal Operations

Cecil V. Parks, Robert M. Westfall, B. L. Broadhead

Nuclear Technology / Volume 87 / Number 3 / November 1989 / Pages 660-678

Technical Paper / TMI-2: Remote Technology and Engineering / Criticality Safety / dx.doi.org/10.13182/NT89-A27718

Beginning in 1984, the Three Mile Island Unit 2 Defueling Design Team requested Oak Ridge National Laboratory to supply criticality safety analyses in support of the licensing activities for all fuel removal operations. The computational methods and basic analytic models employed in the work are discussed, the areas where computational analyses were requested are reviewed, and the pertinent results are tabulated and discussed.