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!
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January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Yuan Chen, Rong Liu, Haipin Guo, Wenmian Jiang, Jian Shen
Fusion Science and Technology | Volume 23 | Number 1 | January 1993 | Pages 68-70
Technical Paper | Blanket Engineering | doi.org/10.13182/FST93-A30120
Articles are hosted by Taylor and Francis Online.
Measurements of 14-MeV neutron leakage multiplication in lead are performed by the total absorption method. A polyethylene sphere is used as the neutron moderator and total absorber. Results from a 235U fission chamber and a 6Li glass detector are analyzed. The measurements are 7% lower than ANISN calculations using ENDF/B-VI.