DocumentCode
2057899
Title
Radiation shielding analysis for DIII-D
Author
Kim, Jinchoon ; Boshoven, J.K. ; Callis, R.W. ; Luxon, J.L. ; Petersen, P.I. ; Su, S.
Author_Institution
Gen. Atomics, San Diego, CA, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
869
Abstract
A radiation shield has been added to the DIII-D tokamak facility to allow an increased neutron production rate without an increased radiation exposure to the public and to personnel. The goal is to reduce the biological dose level at the site boundary by a factor of 300. Shielding analyses were performed extensively using a 3D Monte Carlo neutron-photon coupled code (MCNP) for varied geometry and material combinations. The calculated total dose at the site boundary (83 m from the tokamak) is approximately 10-17 mrem per D-D neutron with the new shield in place, and 3×10-15 mrem without the new shield
Keywords
Monte Carlo methods; dosimetry; fusion reactor safety; radiation protection; shielding; 3D Monte Carlo neutron-photon coupled code; D-D; DIII-D tokamak; biological dose; neutron production rate; radiation shield; shielding analysis; site boundary; Deuterium; Monte Carlo methods; Neutrons; Plasma confinement; Plasma measurements; Plasma sources; Plasma temperature; Plasma x-ray sources; Slabs; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102356
Filename
102356
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