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
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;
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
DOI :
10.1109/FUSION.1989.102356
