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The Theoretical Calculation of the Attenuation of Gamma Radiation from a Swimming Pool Type Reactor

Technical Report ·
DOI:https://doi.org/10.2172/4330853· OSTI ID:4330853
 [1];  [1]
  1. North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
In order to determine the adequacy of the calculational methods employed by Atomics International to solve shielding problems on such reactor systems as the SRE and OMRE, it is required that the results obtained by using these methods be compared with accurate experimental information. Since the only reactor on which such experimental data is available is the Oak Ridge Bulk Shielding Reactor, the theoretical attenuation of gamma radiation in the BSR shield was evaluated. The results were compared with the measurements of the gamma-ray attenuation from this reactor out to a distance of 700 cm from the core. The analysis performed indicates that it is possible to reproduce the measured data quite accurately over the entire range of water thickness for which measurements have been made, the average value of the calculated to measured dose rates being 1.25 with the maximum deviation from this value being less than 19%. The formulation and assumptions necessary in the analysis are discussed. It is concluded that the spectra and method used will yield results which are more than adequate when dealing with shielding analyses, per se, and are probably adequate for heat generation problems as well.
Research Organization:
North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
Sponsoring Organization:
US Atomic Energy Commission (AEC)
DOE Contract Number:
AT(11-1)-GEN-8
NSA Number:
NSA-12-000679
OSTI ID:
4330853
Report Number(s):
NAA-SR--1921
Country of Publication:
United States
Language:
English