ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
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.
John C. Statharas, John G. Bartzis, Demosthenes D. Papailiou
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 248-259
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34476
Articles are hosted by Taylor and Francis Online.
An improved version of the computer code THEAP-2, suitable for calculation of low flows (G < 50 kg/m2·s−1), is developed. The original code failed to provide reasonable agreement with existing experimental data. The discrepancies were attributed mainly to the drift-flux model, the dispersed flow transition criterion, and the correlations for estimating critical heat flux and minimum film boiling temperatures employed in the original code. The Electric Power Research Institute drift-flux model was used to correct these shortcomings and a new dispersed flow transition criterion was proposed. A review and an assessment of the available correlations of the temperatures resulted in the development of revised versions of these correlations. The changes improved the code’s ability to predict quantities such as the wall and vapor temperatures, the actual quality, and the vapor generation rate. The improvements can be attributed to the transition criterion introduced in the revised code.