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
Perpetual Atomics, QSA Global produce Am fuel for nuclear space power
U.K.-based Perpetual Atomics and U.S.-based QSA Global claim to have achieved a major step forward in processing americium dioxide to fuel radioisotope power systems used in space missions. Using an industrially scalable process, the companies said they have turned americium into stable, large-scale ceramic pellets that can be directly integrated into sealed sources for radioisotope power systems, including radioisotope heater units (RHUs) and radioisotope thermoelectric generators (RTGs).
E. A. Fischer
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 105-116
Technical Paper | doi.org/10.13182/NSE77-4
Articles are hosted by Taylor and Francis Online.
Integral measurements of delayed neutron fractions in fast reactor spectra by two different techniques were carried out. The worth of a calibrated 252Cf spontaneous fission source, together with absolute fission rates and with the normalization integral obtained from fission rate mapping, gives experimental values for the effective delayed neutron fraction of a critical assembly. These measurements were performed in three PUO2-UO2 fueled assemblies and in one UO2 fueled assembly. The pile oscillator technique was used to determine relative yields of delayed neutrons from 235U, 238U, and 239Pu. The results confirm the evaluated yields by Tuttle, with a slight bias toward a higher 239Pu yield. With these data, the central worth discrepancy disappears for SNEAK measurements.