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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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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.
G. R. Ansarifar, M. H. Esteki, M. Zaidabadi
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 105-109
Technical Note | doi.org/10.13182/NT15-90
Articles are hosted by Taylor and Francis Online.
Dual-cooled annular nuclear fuel, which is an internally and externally cooled annular fuel, has many advantages for heat transfer. One of the most prominent of these advantages is the ability to harvest more of this type of fuel, which can increase the thermal power of nuclear plants. In this technical note, the core of a VVER-1000 reactor is designed based on the use of internally and externally cooled annular fuels. The thermal-hydraulic parameters of the fuel rods in this type of reactor are analyzed. In addition, the uprate of the thermal power in a VVER-1000 reactor using annular fuels is investigated. For this purpose, first, the proper pitch length of fuel rods in the core is designed under clean and cold conditions using cell and core neutronics calculation codes. Then, thermal-hydraulic calculations are performed for a simulated fuel rod in a hot channel using computational fluid dynamics simulation codes. These calculations are compared with a conventional VVER-1000 reactor that does not use this kind of fuel. One of the most important results of the analysis is that annular fuel shows a sufficient margin for the departure from nucleate boiling and fuel pellet temperature relative to cylindrical fuel. The margin seems viable in accommodating a 129% power uprate.