Nuclear analysis in support of ITER design

摘要

Radiation transport calculations have been carried out to aid in the design of in-vessel components in th International Thermonuclear Experimental Reactor (ITER). The calculations have concentrated on the shielding blanket and vacuum vessel to estimate the neutron and gamma-ray responses in the superconducting toroidal coil assembly and the radiation environment inside the cryostat region. One-dimensional transport methods were used to estimate the overall performance of the in-vessel components and determine the extent to which plasma neutrons are attenuated in the shielding blanket and vacuum vessel. Radiation damage responses in reactor components were also calculated. Multi-dimensional deterministic and Monte Carlo calculations were used to assess specific design problems. This paper summarizes the results of some of the calculations performed to date. The installation at the Garching JWS of radiation transport codes and cross-section data for use by Joint Central Team staff and Home Team analysis is also discussed.