Low temperature irradiations in FFTF (Fast Flux Test Facility)
J.M. Grover, Roger E. Bauer, Raymond J. Puigh, J.R. Thielges
Abstract
J.M. Grover, Roger E. Bauer, Raymond J. Puigh, J.R. Thielges
Abstract
The fusion materials program has little irradiation effects data at temperatures from 100 to 350 {degree}C. Near-term machines such as the International Thermonuclear Engineering Reactor (ITER) will expose materials to neutron doses of 38 to 50 dpa at 150 {degree}C or less. The data base for structural materials must be extended into this range. Also, lower temperatures are needed to investigate the lower bound for tritium release from solid breeder materials. A low temperature test vehicle is proposed for the Fast Flux Test Facility (FFTF), which will provide test temperatures of 100 to 350 {degree}C. An 8.5-cm dia. by 100-cm test volume will be instrumented to collect temperature data and provide feedback for control. The spectrum and flux will provide accelerated damage accumulation for structural materials testing and the best available approximation of fusion reactor conditions for solid breeder materials testing. Breeder samples can be equipped with sweep gas flow lines for tritium recovery tests. 4 refs., 2 figs., 1 tab.
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
The fusion materials program has little irradiation effects data at temperatures from 100 to 350 {degree}C. Near-term machines such as the International Thermonuclear Engineering Reactor (ITER) will expose materials to neutron doses of 38 to 50 dpa at 150 {degree}C or less. The data base for structural materials must be extended into this range. Also, lower temperatures are needed to investigate the lower bound for tritium release from solid breeder materials. A low temperature test vehicle is proposed for the Fast Flux Test Facility (FFTF), which will provide test temperatures of 100 to 350 {degree}C. An 8.5-cm dia. by 100-cm test volume will be instrumented to collect temperature data and provide feedback for control. The spectrum and flux will provide accelerated damage accumulation for structural materials testing and the best available approximation of fusion reactor conditions for solid breeder materials testing. Breeder samples can be equipped with sweep gas flow lines for tritium recovery tests. 4 refs., 2 figs., 1 tab.
Key concepts: Thermonuclear fusion, Breeder (animal), Nuclear engineering, Materials science, Fusion power, Flux (metallurgy), Neutron flux, Nuclear physics