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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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.
N.M. Ghoniem, D.H. Berwald
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 439-444
Materials Engineering | doi.org/10.13182/FST83-A22903
Articles are hosted by Taylor and Francis Online.
Lifetime estimates of blanket components are extremely useful during the design process of fusion reactor blankets. In this paper, we present a preliminary analysis for the performance of HT-9 in the blanket modules of a reference Tandem Mirror Hybrid Reactor (TMHR). We utilize the available data base for HT-9 as well as other ferritic alloys to develop approximate design equations for void swelling, the shift in the ductile-to-brittle-transition temperature (DBTT), and thermal creep rupture at high temperature. HT-9 is used in a relatively low temperature design (below 500°C) to give an allowable design stress on the order of 145 MPa for up to 10 operating years. A minimum structure temperature of 365°C is imposed on the design to ensure a good margin of safety against neutron embrittlement. As an added design feature, the moderate DBTT shifts are almost entirely eliminated by a 450°C anneal for 50–60 hours, once every year. The lifetime of the blanket is estimated to exceed 10 years, and is based on the maximum limit for total elastic plus inelastic strains.