摘要: The European Community International Tokamak Reactor (INTOR-EC) and U.S. Fusion Engineering Device (FED) were used as a basis to investigate the uncertainties of several neutronics performance parameters such as tritium breeding r... 展开 The European Community International Tokamak Reactor (INTOR-EC) and U.S. Fusion Engineering Device (FED) were used as a basis to investigate the uncertainties of several neutronics performance parameters such as tritium breeding ratio in the blanket, atomic displacement rate in the copper stabilizer, and nuclear heating in the epoxy-based insulator that arise due to nuclear data uncertainties and data processing discrepancies. Neutronics calculations were performed and reaction rates estimated for the recent INTOR-EC using the DLC-37 and DLC-41 cross section libraries. In general, the basic cross section data are known accurately enough to determine the tritium breeding ratio of the INTOR-EC within +-2%. The atomic displacement rate and nuclear heating rate in the superconducting magnet of FED (and presumably also INTOR-EC), however, can be predicted to only about +-12% to 24%. If additional accuracy is required, improved measurements of the iron, chromium, and nickel cross sections in the energy range between 12 and 14 MeV will be needed. (Atomindex citation 15:000506) 收起