Actions for A MONTE CARLO METHOD FOR THE ANALYSIS OF GAMMA RADIATION TRANSPORT FROM DISTRIBUTED SOURCES IN LAMINATED SHIELDS

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A MONTE CARLO METHOD FOR THE ANALYSIS OF GAMMA RADIATION TRANSPORT FROM DISTRIBUTED SOURCES IN LAMINATED SHIELDS

Author
Leimdoerfer, M.
Published
[Place of publication not identified] : [publisher not identified], 1964.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1964.
Physical Description
microfiche : negative ; 8 x 13 cm

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Summary
A method for calculating the penetration and energy deposition of gamma radiation, based on Monte Carlo techniques is described. The essential feature is the application of the exponential transformation to promote the transport of penetrating quanta and to balance the steep spatial variations of the source distributions that appear in secondary gamma emission problems. The estimated statistical errors in a number of sample problems, involving concrete shields with thicknesses up to 500 cm, are shown to be quite favorable, even at relatively short computing times. A practical reactor shielding problem is also shown, and the predictions are compared with measurements. (auth)
Report Numbers
NP-13626
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
NSA number: NSA-18-015423
OSTI Identifier 4081099
Research organization: Sweden. Forsvarets Forskningsanstalt, Stockholm.
View MARC record | catkey: 41356880