DIII-D Safety Procedures and Operational Experience.

摘要

The DIII-D research tokamak, which has near reactor dimensions, has been operating for approximately ten years. The hazards at the facility include high voltages, high currents, cryogenics, radiation, and normal industrial hazards. Procedures have been developed for operating the device, minimizing both the hazards to personnel and the damage caused by equipment failures, and for logging of failures. The machine and the neutral beamlines have been operated in hydrogen and are now starting operation in deuterium to expand the machine capabilities to reactor relevant regimes. Deuterium operation creates a significant amount of neutrons and therefore a neutron shield is being built around the machine area to reduce personnel radiation to As Low As Reasonably Achievable (ALARA) and to keep radiation at the site boundary at or below a limit of 20 mrem per calendar year. Gamma radiation shielding walls have been in place since the initial machine construction. The safety procedures for the DIII-D facility will be outlined and the accident experience will be discussed together with the neutron radiation monitoring program being developed. 4 figs., 3 tabs.