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
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
Brian J. Laundy, Owen N. Jarvis
Fusion Science and Technology | Volume 24 | Number 2 | September 1993 | Pages 150-160
Technical Paper | Experimental Device | doi.org/10.13182/FST93-A30221
Articles are hosted by Taylor and Francis Online.
A simple computer model of the Joint European Torus (JET) tokamak has been constructed, using the neutron transport code McBEND, to assist in the interpretation of point neutron source data used for empirical calibrations of fission chambers placed near the tokamak to measure the total neutron emission from deuterium and deuterium-tritium plasmas, A satisfactory simulation of the experimental data using a 252Cf neutron source is obtained. In particular, the preferential moderation and absorption of 252Cf neutrons, compared with plasma neutrons, resulting from the buildup of equipment around the tokamak in recent years is demonstrated; this differentiation between neutron sources is a consequence of the use of a concrete filler in the spaces between the toroidal field (TF) coils. An unexpected increase in detector response is explained by the substitution of Freon for water as the TF coil coolant. Finally, the McBEND calculations are found to predict correctly the relative responses of both 235U and 238U fission chambers to 2.5- and 14-MeV plasma neutrons.