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
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!
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July 2025
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Latest News
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
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.
