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.
Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
T. Izak-Biran, S. Amiel
Nuclear Science and Engineering | Volume 57 | Number 2 | June 1975 | Pages 117-121
Technical Paper | doi.org/10.13182/NSE75-A27339
Articles are hosted by Taylor and Francis Online.
The emission probabilities of delayed neutrons are reevaluated on the basis of recently determined fission yields. The accuracy of the probabilities for thermal and fast fission of 233U and 235U is examined by summation of the individual delayed-neutron yields of the precursors and by comparison with the unseparated group and directly measured total delayed-neutron yields. The good agreement of the results obtained by the two independent methods indicates that the derived probabilities are accurate enough for the calculation of delayed-neutr on yields for other fissioning systems and for reactor calculations.
