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.
P. K. Job, M. Srinivasan
Nuclear Science and Engineering | Volume 85 | Number 4 | December 1983 | Pages 422-425
Technical Note | doi.org/10.13182/NSE83-A18388
Articles are hosted by Taylor and Francis Online.
It has been shown that the “minimum” achievable spherical critical masses for the three main fissile isotopes of 235U, 239Pu, and 233U at normal temperature and density with BeH2 as moderator and with a thick 9Be reflector is lower than for any other system reported so far. In this context the feasibility of decreasing the critical masses further by exploiting the Bragg cutoff phenomenon in cooled beryllium reflectors was investigated. The reactivity gain obtainable in cooling part (or whole) of the beryllium reflector of a BeH2-moderated homogeneous 233U system to liquid nitrogen temperature (78 K) is explored. Transport theory calculations show that a 50-cm two-zone beryllium reflector with a cooled inner zone of optimum thickness (∼15 cm) at 78 K has an improved albedo and results in a further reduction of 6 to 8% in the critical mass.