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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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.
Hongdong Zhen, Songtao Yin, Lei Zhang, Ningning Wang, Bo Xu, Haijun Wang
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 54-61
Technical Paper | doi.org/10.1080/00295450.2020.1739994
Articles are hosted by Taylor and Francis Online.
This paper aims to revise the critical flow criterion and flashing inception of the analytical critical flow model and to further explore the effect of upstream conditions on critical mass fluxes. The flashing inception of the model is considered to be affected by the Reynolds number and the Jakob number. Model predictions show strong similarities with test results compared with other models, with average errors of less than 10.1% for simulated slits and 15.8% for natural cracks. Upstream parameters of the liquid, such as the stagnation pressure, subcooling, and aspect ratio, directly influence the rate of depressurization, the thermodynamic nonequilibrium constant, and the friction pressure drop, respectively, which determine the critical mass flux. This research provides the theoretical basis for accurate assessment of critical crack, providing safeguards for monitoring nuclear reactor leaks.