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.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
Eldon Schmidt, Philip F. Rose
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 300-304
Technical Note | doi.org/10.13182/NSE83-A17800
Articles are hosted by Taylor and Francis Online.
A modern continuous energy-angle Monte Carlo program has been used to perform neutron shielding calculations for a fusion shield. The SAM-CE Monte Carlo program developed by the Mathematical Applications Group has been used for a demonstration calculation of an Oak Ridge National Laboratory fusion shield benchmark with a deuterium-tritium neutron source. Calculations were made for three shielding configurations. They were compared with experiment and also with previous calculations using Sn with first- and last-flight modifications. Agreement with experiment was found to be good at high (>14-MeV) and low (<5-MeV) energies. At intermediate energies where the fluxes are much lower, the agreement was less accurate differing by as much as factors of 2 or 3 in extreme cases. An improved resolution broadening function for the NE-213 detectors helped reduce some of these differences.