Radiation Field Estimation for the Diagnostic and Control Components by Monte Carlo Neutronics Calculations with LHD 3-Dimensional Modeling

摘要

The precise estimation of the radiation field is required to evaluate the soundness of the diagnostic and control components for the LHD deuterium experiment. Monte Carlo neutron calculations are carried out with three-dimensional modeling of LHD using MCNP-6 code with the cross-section library of ENDF B-VI. Three-dimensional map of the total neutron flux, neutron and gamma-ray spectra, and the dose rate profile are obtained. Neutron and gamma fluxes by MCNP-6 code are about 2/3 of those by DORT code, which is probably due to the two-dimensional modeling of the DORT calculation. The gamma-ray absorbed dose for Si is 20-70 Gy during nine years operation, where high integrated electric devices such as the programmable logic controller (PLC) may survive if we consider the gamma-ray effect only.