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Criticality Prevention During Postaccident Decontamination of Three Mile Island Unit 2 Plant Systems

Gerald L. Palau

Nuclear Technology / Volume 87 / Number 3 / November 1989 / Pages 679-682

Technical Paper / TMI-2: Remote Technology and Engineering / Criticality Safety / dx.doi.org/10.13182/NT89-A27719

During the accident at Three Mile Island Unit 2 (TMI-2), small quantities of fuel material were transported to plant piping systems outside the reactor coolant system (RCS). The likelihood of a criticality outside of the RCS during the cleanup of the plant systems was very small; however, given the consequence of any possible critical event in the TMI-2 systems, it was always necessary to ensure that all steps were taken to prevent criticality. Therefore, engineered controls were developed to ensure that decontamination of plant systems containing fuel material could be conducted in a manner that precluded criticality.