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Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility

by Georgeta Radulescu, Thomas M Miller, Kaushik Banerjee, Douglas E Peplow
Publication Type
Conference Paper
Journal Name
Transactions of the American Nuclear Society
Publication Date
Page Numbers
765 to 768
Volume
118
Issue
1
Conference Name
ANS Annual Meeting 2018
Conference Location
Philadelphia, Pennsylvania, United States of America
Conference Sponsor
ANS
Conference Date
-

This paper presents a confirmatory dose rate calculation for a proposed consolidated interim spent nuclear fuel (SNF) storage facility (CISF). The proposed CISF was modeled in detail using SCALE 6.2.1 to determine the radiation dose map of the surrounding areas of the facility and determine the location of the controlled area boundary based on 10 CFR 72.104 requirements. The spatial dose rate distribution was determined as the total dose rate contributions by each of the 467 storage casks comprising the CISF. A rectangular boundary outside of which no dose rate exceeds 25 mrem/yr has the dimensions of 1.25 km  1.25 km. It denotes the smallest rectangle that could serve as the controlled area boundary. The results (dose map) show the unique capability of the SCALE code system for a high-resolution radiation dose simulation of a large SNF storage facility.