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.
S. N. Cramer, E. M. Oblow
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 532-549
Technical Paper | doi.org/10.13182/NSE77-A26990
Articles are hosted by Taylor and Francis Online.
Monte Carlo transport calculations were made to analyze the results of two integral measurements of neutron scattering and gamma-ray production from liquid nitrogen samples. The experimental data from Intelcom Radiation Technology and Oak Ridge National Laboratory (ORNL) were given as angular-dependent NE-213 detector count rates of neutrons and gamma rays scattered from a spherical nitrogen Dewar pulsed with a 1- to 20-MeV neutron source. ORNL results also included unfolded neutron and gamma-ray spectra as a function of detector angle in broad incident neutron energy bins. Multigroup Monte Carlo calculations using the MORSE code and ENDF/B-IV nitrogen cross-section data were made to analyze all reported results. Comparisons of calculated and measured results indicate that no major deficiencies exist in the ENDF/B-IV gamma-ray production data, in contrast to the conclusions drawn from studies in previous years. Deficiencies, however, were found in the neutron data, primarily in the elastic and inelastic data above 9 MeV and in the elastic angular distribution data around 5 MeV.