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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
I. K. Park, J. H. Kim, S. H. Hong, S. W. Hong
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 302-314
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16981
Articles are hosted by Taylor and Francis Online.
The Test for Real cOrium Interaction with water (TROI) experiments have been performed to reveal unsolved issues of a steam explosion using real core material at the Korea Atomic Energy Research Institute. One of the findings from the TROI experiments is that the results of a fuel coolant interaction (FCI) are strongly dependent on the composition of corium, which is composed of UO2, ZrO2, Zr, and steel.The TROI tests were analyzed in view of a particle size response for various types of fuel coolant explosions. This can provide an understanding about the relationship between an initial condition, the mixing, and the explosion. The particle size distribution data from the TROI tests and a single-particle film boiling model were used for all these analyses.The difference between a quenched FCI and an explosive FCI was defined by comparing the final particle size. This analysis indicates that an explosive FCI resulted in a large amount of fine particles and in a small amount of large-sized particles. With this, the mixing size of the particles that participate in the steam explosion and the fine-particle size produced from a steam explosion can be defined in the TROI test.The particle size distributions of the quenched TROI tests were then considered. We note that the explosive test results cannot provide information on the mixing process. This analysis on the particle size indicates that a self-triggered system includes large-sized particles to participate in a steam explosion, but a non-self-triggered system includes smaller-sized particles and more fine-sized particles.Finally, the explosion potentials of the quenched TROI tests were compared to each other. Thus, the single-particle film boiling model based on the particle size distribution provides the explanation for the explosion behaviors of a variety of melts.