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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
C. M. Cooling, M. M. R. Williams, E. T. Nygaard, M. D. Eaton
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 233-259
Technical Paper | doi.org/10.13182/NSE13-55
Articles are hosted by Taylor and Francis Online.
Previously, a point kinetics model of the Medical Isotope Production Reactor has been presented, which included representations of instantaneous power, delayed neutron precursors, fuel solution temperature, radiolytic gas content, and coolant temperature. This model has been extended to include the effects of a vertically discretized temperature profile with a mixing of heat energy by eddies, boiling, and condensation and an extended model of bubble velocity and radius. It is found that the most striking change to the behavior of the system is caused by the effects of steam, which provides a strong negative feedback that tends to depress average powers in cases where the fuel solution temperature rises above the saturation temperature but can also lead to large, sharp power peaks through steam exiting the system (which can remove a large amount of negative reactivity in a short amount of time). The overall effect, however, does not lead to any unbounded power excursions. Possibilities for further extension of the model include the modeling of the composition of the plenum gas and the modeling of global pressure and its effects.