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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
D. C. Baxter, A. E. Dabiri, J. E. Glancy, W. K. Hagan
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 599-602
Fusion System Studies | doi.org/10.13182/FST83-A22927
Articles are hosted by Taylor and Francis Online.
A tokamak reactor systems code has been developed by combining a previously developed plasma engineering code with an existing reactor systems code and adding calculations for thermal hydraulics, stress analysis, physical sputtering, and neutron activation dose rate. Calculations from the thermal hydraulics and neutron activation dose rate modules are compared with results from more complex codes. The effects on reactor performance of unpredictable properties such as plasma profiles and confinement times are demonstrated.