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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
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.