Radiation shielding analysis for DIII-D

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 perf...

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Bibliographic Details
Published inIEEE Thirteenth Symposium on Fusion Engineering pp. 869 - 873 vol.2
Main Authors Kim, J., Boshoven, J.K., Callis, R.W., Luxon, J.L., Petersen, P.I., Su, S.
Format Conference Proceeding
LanguageEnglish
Published IEEE 1989
Subjects
Deuterium
Monte Carlo methods
Neutrons
Plasma confinement
Plasma measurements
Plasma sources
Plasma temperature
Plasma x-ray sources
Slabs
Tokamaks
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Summary: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/sup -17/ mrem per D-D neutron with the new shield in place, and 3*10/sup -15/ mrem without the new shield.< >
DOI:10.1109/FUSION.1989.102356