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. G. Mooney
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 157-172
Technical Paper | doi.org/10.13182/NSE71-A19664
Articles are hosted by Taylor and Francis Online.
Calculations were performed to determine energy and angle distributions of the fission-product gamma ray, air-ground secondary gamma ray, and neutron fluence incident on structures resulting from the detonation of a representative intermediate-yield thermonuclear weapon 100 m above the ground. These energy and angle distributions were used as input data to the ANISN discrete ordinates code to calculate the penetration of the radiation through various thicknesses of type O-HW1 concrete. The production and transport of concrete capture gamma rays were calculated in tandem with the neutron transport. The penetration results were used to calculate the various radiation components at the center of a simple concrete blockhouse. The inside lengths and widths of the structure varied from 10 to 50 ft and the inside height was fixed at 10 ft. Wall and roof thicknesses varied from 6 to 60 in. The results of the calculations were expressed as structure protection coefficients (dose at the receiver per unit free-field dose). The neutron dose was found to contribute the highest fraction of the total dose for wall and roof thicknesses up to 12 in. For thicknesses of 18 in. and more, the airground secondary gamma rays and concrete capture gamma rays were found to dominate, becoming increasingly more important with increasing thickness. The relative magnitude of each component did not vary significantly with structure size; however, all components were found to decrease with an increase in structure size for a given wall and roof thickness.