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Implications of an ICRP 30 consistent control room dose model

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7168377
A control room with a high unfiltered inleakage was evaluated for postaccident doses. Doses were calculated using the latest regulatory guidance, as provided in Standard Review Plan (SRP) 6.5.2. Two sets of dose conversion factors (DCFs) were utilized for comparison: Regulatory Guide 1.109 and ICRP 30 from the International Commission on Radiological Protection. Source terms were based on TID-14844 and a 2800-MW(thermal) power level was used. It was assumed that 25% of the core iodines and 100% of the noble gases are instantaneously released to the containment at the onset of the accident (per Regulatory Guide 1.4). The containment volume above the operating deck was assumed to be sprayed, the rest unsprayed, with mixing between the two regions at 23.6m{sup 3}/s (50000 ft{sup 3}/min). Two decay cases were evaluated; daughter products were neglected in one and considered in the other.
OSTI ID:
7168377
Report Number(s):
CONF-911107--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
Country of Publication:
United States
Language:
English

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