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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
Latest News
DOE, General Matter team up for new fuel mission at Hanford
The Department of Energy's Office of Environmental Management (EM) on Tuesday announced a partnership with California-based nuclear fuel company General Matter for the potential use of the long-idle Fuels and Materials Examination Facility (FMEF) at the Hanford Site in Washington state.
According to the announcement, the DOE and General Matter have signed a lease to explore the FMEF's potential to be used for advanced nuclear fuel cycle technologies and materials, in part to help satisfy the predicted future requirements of artificial intelligence.
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 143-148
Technical Paper | doi.org/10.13182/NSE77-A27017
Articles are hosted by Taylor and Francis Online.
The average 240Pu capture cross section was measured from 200 eV to 350 keV. The cross section was normalized at thermal-neutron energies (0.02 to 0.03 eV), and this normalization was confirmed at the 1.06-eV resonance by the black resonance technique. The source of pulsed neutrons was the Oak Ridge Electron Linear Accelerator. The capture gamma-ray detector used was the “total energy detector,” which is a modification of the Moxon-Rae detector. The shape of the neutron flux was measured relative to the 10B(n, α) cross section up to 2 keV and the 6Li(n, α) cross section at higher neutron energies. The results of the measurement define the average capture cross section of 240Pu over a wide neutron energy range to an accuracy of ∼8%, which is significantly better than previously known. The results indicate that the ENDF/B-IV evaluation is ∼25% low above 30-keV neutron energy. The cross section is important in fast plutonium-fueled reactors.