Nuclear data needs for FMIT
The Fusion Material Irradiation Testing Facility (FMIT) is designed to test samples in a high energy neutron environment so that data obtained in fission reactors can be extrapolated to that needed in fusion devices. Although most of the flux is centered around approx. 14 MeV, the neutron distribution will extend from thermal energies to 50 MeV. Data needed in design include total, elastic, and removal cross sections for shielding, neutron yields for source calculations, and selected transmutation cross sections for dose determinations. Data needed for operation include transport and dosimetry cross sections for flux determinations, damage energy, transmutation, and gas production cross sections for damage analyses, and selected data for machine operation and maintenance. Detailed reaction lists are given.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 5822396
- Report Number(s):
- HEDL-SA-1902-FP; CONF-791058-43
- Country of Publication:
- United States
- Language:
- English
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