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. Boersma-Klein, J. Kistemaker
Fusion Science and Technology | Volume 20 | Number 4 | December 1991 | Pages 610-614
Advanced Fission Reactors | doi.org/10.13182/FST91-A11946906
Articles are hosted by Taylor and Francis Online.
Because of the steep temperature profile in a gas core fission reactor, various heat transfer processes are involved. The purpose of this work was to investigate the eventual existence of a gas blanket near the wall of the reactor, where kinetic heat transfer dominates. We define the gas blanket as the distance from the wall where the kinetic heat transfer equals the radiative one. We find that for a spherical reactor with a radius of 2 m, the gas blanket has a size of
0.8 m for a thermal power of 5 MW
0.5 m for a thermal power of 10 MW
0.2 m for a thermal power of 50 MW
For a reactor operating with a thermal power of 1MW the kinetic heat flux is always higher than the radiative one.