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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Nuclear Dirigo
On April 22, 1959, Rear Admiral George J. King, superintendent of the Maine Maritime Academy, announced that following the completion of the 1960 training cruise, cadets would begin the study of nuclear engineering. Courses at that time included radiation physics, reactor control and instrumentation, reactor theory and engineering, thermodynamics, shielding, core design, reactor maintenance, and nuclear aspects.
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.