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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Latest News
Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
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.