Home / Publications / Journals / Nuclear Technology / Volume 87 / Number 4
Nuclear Technology / Volume 87 / Number 4 / December 1989 / Pages 1013-1020
Late Paper / TMI-2: Decontamination and Waste Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A27693
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The source range monitor (SRM) response during the first 25 h of the Three Mile Island Unit 2 (TMI-2) accident is analyzed. The response of the SRM was simulated by performing static neutron transport calculations on a variety of lower head core material distribution models. Using the previously derived core and lower head material configurations at 225 min and 3 yr after shutdown as starting points, the changing lower head material distribution during the period from 225 min to 25 h after shutdown was estimated. The estimated lower head material distribution derived from this transport analysis appears to be consistent with other studies performed under the auspices of the TMI-2 accident evaluation program.