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.
Eiping Quang, Glenn F. Knoll
Nuclear Science and Engineering | Volume 110 | Number 3 | March 1992 | Pages 282-288
Technical Paper | doi.org/10.13182/NSE90-99
Articles are hosted by Taylor and Francis Online.
The cross section of the reaction 238U(n,γ)239U is measured at neutron energies of 23 and 964 keV. Photoneutron sources Sb-Be and Na-Be are calibrated using a manganese bath traceable to the National Bureau of Standards neutron source NBS-I and are provided nearly monoenergetic neutron irradiation. Neptunium-239 from the decay of 239U is chemically separated from the uranium target and is counted to determine the reaction rate. An 242Am foil is used as an absolute gamma-ray calibration standard in the determination of the induced activity. The resulting cross-section values are 491 ± 11 and 138 ± 5 mb at 23 and 967 keV, respectively.
