ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Helmut Holzbauer, Lothar Wolf
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 166-181
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2940
Articles are hosted by Taylor and Francis Online.
GOTHIC is an advanced code for thermal-hydraulic flow simulation in nuclear reactor containments and other confinements. Battelle Europe has participated in the development and verification of the code over a number of years.Described are blind and open posttest calculations of the Heiss Dampf Reaktor hydrogen-mixing experiments E11.2 and E11.4 in comparison with measured data.Caused by a miscalibration of steam source flow rates and neglect of the heat sink capability of the instrumentation cooling lines, the pressure, temperature, and steam concentrations were drastically overpredicted by the blind predictions and are quantitatively not comparable to experimental data.The following conclusions can be drawn from the parametric open posttest calculations:1. Scenarios with homogeneous containment atmosphere (like E11.4) can be simulated accurately with lumped-parameter models.2. The lumped-parameter method is seemingly not fully qualified to predict the hydrogen distribution in a stratified containment atmosphere (like E11.2).3. Improved predictive quality may require the application of distributed parameter models.