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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
G. Kennedy, K. Van Tichelen (SCK-CEN), J. Pacio (KIT), I. Di Piazza (ENEA), H. Uitslag-Doolaard (NRG)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 505-519
In recent years, extensive thermal-hydraulic experimental tests have been performed on the LBE-cooled, wire-wrapped fuel assembly of MYRRHA. These thermal-hydraulic tests were performed using fuel assembly mock-ups, in large-scale LBE experimental test facilities at SCK•CEN (Belgium), ENEA (Italy) and KIT (Germany). The fuel assembly pressure drop characteristics and flow induced vibration characteristics were tested with a full-scale 127-pin mock-up test section. The existing pressure drop correlations of Rehme and Cheng and Todreas (simplified model) predict the experimental pressure drop data very well and are considered suitable for use in the design and safety analysis of the MYRRHA system. Flow induced vibrations are very limited in the wire-wrapped bundle and fuel pin fatigue damage from vibration during operation is not expected. Further analysis and testing is required to determine if damage from fretting corrosion could be expected.
Heat transfer characteristics of the fuel assembly were investigated experimentally in two separate 19-pin heated rod test sections, cooled by LBE. The existing Kazimi-Carelli correlation predicts the global average Nusselt numbers very well, but the correlation is not developed to capture local hot-spots. For the fuel assembly safety analysis, a hot-spot factor is defined and analysed to determine the hot-spot temperature penalty, to further determine operational safety margins.
