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MORSE Monte Carlo shielding calculations for the zirconium hydride reference reactorVerification of DOT-SPACETRAN transport calculations of a lithium hydride and tungsten shield for a SNAP reactor was performed using the MORSE (Monte Carlo) code. Transport of both neutrons and gamma rays was considered. Importance sampling was utilized in the MORSE calculations. Several quantities internal to the shield, as well as dose at several points outside of the configuration, were in satisfactory agreement with the DOT calculations of the same.
Document ID
19720010043
Document Type
Conference Paper
Authors
Burgart, C. E. (Oak Ridge National Lab. TN, United States)
Date Acquired
August 6, 2013
Publication Date
January 1, 1972
Publication Information
Publication: NASA, Washington Proc. of the Natl. Symp. on Nat. and Manmade Radiation in Space
Subject Category
NUCLEAR ENGINEERING
Distribution Limits
Public
Copyright
Work of the US Gov. Public Use Permitted.

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IDRelationTitle19720009951Analytic PrimaryProceedings of the National Symposium on Natural and Manmade Radiation in Space