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
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
J. A. Ulseth, J. W. Helm
Nuclear Technology | Volume 3 | Number 4 | April 1967 | Pages 233-239
Technical Paper and Note | doi.org/10.13182/NT67-A27762
Articles are hosted by Taylor and Francis Online.
A study was made to determine the changes in fast flux intensity and spectra in several irradiation positions of the General Electric Test Reactor caused by varying the material composition in an irradiation cell or in surrounding reactor positions. The material changes are typical of those that could be expected to occur during a long-term irradiation in a test reactor. It has been concluded that material changes within an irradiation cell do perturb the fast neutron spectrum and change the fast flux within that cell. Changes made in surrounding cells do not significantly alter the spectrum in the irradiation cell. Consequently, the fast flux based on the spectral-averaged cross section and the damage indexes used for correlation of data on materials are not altered significantly. Therefore, once a detailed spectral calculation has been made, a new calculation is not required for each change in core loading.