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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
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.
P. A. Finn, E. H. Van Deventer
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 783-790
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25230
Articles are hosted by Taylor and Francis Online.
The heterogeneous reaction between oxygen/helium gas, tritium and stainless steel was studied at the back surface of a stainless steel tube. The yield of tritiated water was determined as a function of oxygen concentration, tritium concentration, protium concentration, flow rate, and temperature. This report describes the results for two sets of runs done at 550°C with and without 15 ppm protium in the oxygen/helium gas. At oxygen concentrations of 40 ppm, the presence of excess protium in the oxygen/ helium produced a reduced yield of tritiated water. At oxygen concentrations >1000 ppm, the two yields were equivalent, 98%.
