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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
NECX debut: Shaping the next era of energy
The sold-out inaugural Nuclear Energy Conference & Expo (NECX) got off to a bumping start in Atlanta, Ga., Tuesday morning with an opening plenary that felt like part dance party and part highlight reel showing off the latest industry achievements.
That intro left the audience pumped up for Entergy’s CEO and NEI chair Drew Marsh, who welcomed everyone to the event, hosted jointly by the American Nuclear Society and the Nuclear Energy Institute. He spoke to a full house of more than 1,300 attendees, promising a blend of science, technology, policy, and advocacy centered around the future of nuclear energy.
L. B. Prus, E. S. Byron, F. O. Von Plinsky, S. W. Porembka
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 167-173
Technical Paper | doi.org/10.13182/NSE59-A25656
Articles are hosted by Taylor and Francis Online.
A study of the extrusion and fabrication characteristics of various titanium-enriched boron dispersions indicate that hot extrusion of uncompacted powders is a feasible method for producing these materials. Tensile and impact properties of dispersions containing 2.43, 3.4, and 3.8 w/o B10 show a decrease with increasing B10 concentration. Irradiation studies on these materials revealed that internal cracking results after thermal neutron exposures of approximately 4.6 × 1020 nvt and higher. Tensile properties of the dispersions were related directly to the exposure and resulting structure, however, no correlation was found between exposure and impact properties of these materials.
