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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
R. E. Dahl, H. H. Yoshikawa
Nuclear Science and Engineering | Volume 21 | Number 3 | March 1965 | Pages 312-318
Technical Paper | doi.org/10.13182/NSE65-A20034
Articles are hosted by Taylor and Francis Online.
A neutron-exposure unit for radiation-damage studies is derived which is proportional to gross-displacement production with little dependence on the reactor spectra or displacement model selected. The unit is applied to the analysis of irradiation-induced changes in nil-ductility temperature in steel. Data from a graphite reactor and from the core of a water-moderated test reactor were statistically distinct as originally reported. Through the application of this unit, these results could be reconciled to constitute a single body of data.