IFMIF (International Fusion Materials Irradiation Facility), an accelerator-based neutron source for fusion components irradiation testing: Materials testing capabilities
The International Fusion Materials Irradiation Facility (IFMIF) is proposed as an advanced accelerator-based neutron source for high-flux irradiation testing of large-sized fusion reactor components. The facility would require only small extensions to existing accelerator and target technology originally developed for the Fusion Materials Irradiation Test (FMIT) facility. At the extended facility, neutrons would be produced by a 0.1-A beam of 35-MeV deuterons incident upon a liquid lithium target. The volume available for high-flux (>10/sup 15/ n/cm/sup 2/-s) testing in IFMITF would be over a liter, a factor of about three larger than in the FMIT facility. This is because the effective beam current of 35-MeV deuterons on target can be increased by a factor of ten to 1A or more. Such an increase can be accomplished by funneling beams of deuterium ions from the radio-frequency quadruple into a linear accelerator and by taking advantage of recent developments in accelerator technology. Multiple beams and large total current allow great variety in available testing. For example, multiple simultaneous experiments, and great flexibility in tailoring spatial distributions of flux and spectra can be achieved. 5 refs., 2 figs., 1 tab.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 7078485
- Report Number(s):
- WHC-SA-0328; CONF-881031-24; ON: DE89001919
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACCELERATORS
ALKALI METALS
ELEMENTS
LINEAR ACCELERATORS
LITHIUM
MATERIALS
MATERIALS TESTING
METALS
NEUTRON SOURCES
PARTICLE SOURCES
RADIATION SOURCES
TESTING
THERMONUCLEAR REACTOR MATERIALS