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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
W. L. Barr, R. H. Bulmer, L. J. Perkins, S. A. Cohen, K. A. Werley
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1416-1420
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST92-A29920
Articles are hosted by Taylor and Francis Online.
We have just completed a comparison of predictions for the scrape-off layer (SOL) plasma, from a physics model [1] with the more accurate ones from a two-dimensional fluid code, the B2 code [2]. The results presented here show rather good agreement on values of plasma temperature in the SOL and of divertor heat load, for a rather wide range of Tokamak sizes and parameters. We are therefore confident that this model will provide a suitable divertor module for both the new ITER systems code, SUPERCODE [3], and other applications requiring fast but accurate modelling of edge plasma parameters, at least within the range of the present benchmarks.