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.
S. Nagy, S. Daróczy, P. Raics, I. Boda, and I. Matajsz
Nuclear Science and Engineering | Volume 88 | Number 2 | October 1984 | Pages 154-163
Technical Paper | doi.org/10.13182/NSE84-A28399
Articles are hosted by Taylor and Francis Online.
Different empirical and semiempirical systematics have been developed to predict unmeasured fission product yields. One of these methods, originally proposed by Musgrove et al. and developed by Cook et al., is used to describe the energy dependence of the mass distribution in neutron-induced fission of 238U utilizing published yield data. The available measured cumulative yields of fission products are collected for monoenergetic 238U(n, f) processes. The mass distributions at approximate neutron energies of 1.5, 2.0, 3.0, 3.9, 5.2, 6.0, 7.0, 7.9, 9.0, and 14.7 MeV are fitted by the sum of five Gaussian functions. The energy dependence of the parameters of the Gaussian functions can also be described by semiempirical formulas. The 2σ error of the mass yields calculated by the fitted parameters can be estimated to be ∼10% in the peak regions and 20% in the valley region for the above neutron energies. The formulas with the given parameters can be useful in estimating unmeasured 238U fission product yields for any monoenergetic and nonmonoenergetic neutron irradiations in the range of 1.5 to 15 MeV. The method has been tested in a study of the 238U fission by neutrons having a Watt spectrum produced in the thermal fission of235U.