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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
D. L. Jassby, S. S. Kalsi
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1052-1057
Next-Generation Devices | doi.org/10.13182/FST83-A22997
Articles are hosted by Taylor and Francis Online.
The principal purpose of the FED-R tokamak facility is to provide a substantial quasi-steady flux of fusion neutrons irradiating a large test area in order to carry out thermal, neutronic and radiation effects testing of experimental blanket assemblies. The emphasis on reliable nuclear testing capability demands that the plasma physics characteristics and technological features of the fusion machine be chosen as close to mid-1980s' state of the art as possible, with the important exception that FED-R requires high-duty-factor operation. The outboard nuclear test region is at least 80 em deep with approximately 60 m2 of exposure area. The neutron wall loading is 0.4 MW/m2 in Stage I operation (Qp =1.5) and 1.3 MW/m2 in Stage II (Qp =2.5). Thg toroidal field coils are fabricated of water-cooled copper plates with demountable joints and operate steady state with a power dissipation of 180 MW in Stage I and 280 MW in Stage II.