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2024 ANS Annual Conference
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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.
P. Y. Hsu, L. G. Miller, G. A. Deis, Y. D. Harker, G. R. Longhurst, T. S. Born, E. H. Ottewitte, K. D. Watts
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1216-1221
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A23023
Articles are hosted by Taylor and Francis Online.
A large-volume, distributed, pulsed, 14 MeV neutron source, which utilizes the high powered (270-GW) Power Burst Facility (PBF) at the Idaho National Engineering Laboratory, is described. The concept of utilizing existing fission test reactors to test fusion first wall/blanket (FW/B) components and systems has been adequately documented. In all previous scenarios, the normal fission spectrum (including tailoring) was shown to produce adequate heating profiles and some tritium breeding. However, one recognized shortcoming has been the absence of the 14 MeV neutron component. This paper describes a scheme whereby the fission neutrons would be employed to produce the desired 14 MeV component. The data obtained from tests in this large-volume [20 em (8 in.) in diameter and 90 em (36 in.) in length], distributed neutron source will pertain to both near-term (Tokamak Fusion Test Reactor—TFTR) and future pulsed fusion machines. Specifically, application requiring high flux but low fluence is foreseen in the areas of dosimetry benchmarking for tritium breeding performance code verification. As a general purpose, FW/B integrated technology development capability, the PBF is shown to be pertinent to addressing the bulk-heated, solid breeder blanket thermal and mechanical issues; tritium permeation in the presence of radiation, and barrier development in the prototypical radiation environment associated with the first wall; issues associated with the technology of breeder materials; and in situ tritium recovery process characterization and system development.