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TMI-2 Reactor Coolant System Criticality Analyses

Conference · · Transactions of the American Nuclear Society
OSTI ID:6665290
 [1];  [1]
  1. Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)
Recent work at Oak Ridge National Laboratory has focused on criticality assessments of configurations pertinent to the Three Mile Island Unit 2 (TMI-2) defueling. The TMI-2 Criticality Task force has adopted a bounding approach in defining a concentration of soluble boron that would maintain the core in a shutdown condition for all fuel removal operations. The analytical models and procedures employed in the design-basis study for establishing this limiting boron concentration were recently reported. This summary reports extensions to the design-basis study in two areas: (a) consideration of fuel particle sizes larger than the original UO2 pellet and (b) introduction of various foreign materials into the fuel rubble during defueling operations.
Research Organization:
Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
OSTI ID:
6665290
Report Number(s):
CONF-860610-
Conference Information:
Journal Name: Transactions of the American Nuclear Society Journal Volume: 52
Country of Publication:
United States
Language:
English

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