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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
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.
Jungchung Jung
Fusion Science and Technology | Volume 4 | Number 1 | July 1983 | Pages 144-163
Technical Paper | Fusion Reactors | doi.org/10.13182/FST83-A22781
Articles are hosted by Taylor and Francis Online.
An in-depth nuclear analysis has been performed for WILDCAT that is a conceptual design of a commercial tokamak reactor utilizing a catalyzed deuterium-deuterium (D-D) fusion fuel cycle. Comparisons are made with the deuterium-tritium-fueled STARFIRE design in order to identify the salient features of D-D tokamak reactor designs. Since WILDCAT does not have to breed tritium, the blanket and shield system can be optimized to have a thinner inboard extent (∼0.8 versus 1.2 m for STARFIRE) leading to more efficient use of the toroidal field. The nonbreeding blanket concept of WILDCAT can also be utilized for substantial enhancement of the system energy multiplication (2.02 versus 1.14). These benefits help to overcome the reduced fusion reactivities and lead to a 60% more efficient blanket in terms of power generation. The outboard blanket and shield'system has been designed for personnel access within 24 h after reactor shutdown and uses as much as possible materials that are not resource limited and that have lower activation. Ninety percent of the materials in WILDCAT can be recycled within 50 yr after their discharge from the reactor.