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.
M. E. Sawan, L. A. El-Guebaly
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2069-2074
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30026
Articles are hosted by Taylor and Francis Online.
An efficient organic cooled low activation ferritic steel first wall and shield has been designed for the D-3He power reactor ARIES-III. The inboard shield is 65 cm thick and provides adequate magnet protection. The steel structure has a peak end-of-life damage of only 63 dpa and is expected to last for the whole reactor life. The total absorbed dose rate in the organic coolant is 1026 eV/s resulting in a radiolytic decomposition rate of 171 kg/hr. Tritium production leads to a release rate of 33.5 Ci/d and an acceptable off-site effluent dose < 1.3 mrem/yr.
