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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
World Bank, IAEA partner to fund nuclear energy
The World Bank and the International Atomic Energy Agency signed an agreement last week to cooperate on the construction and financing of advanced nuclear projects in developing countries, marking the first partnership since the bank ended its ban on funding for nuclear energy projects.
D. H. Meikrantz, J. D. Baker, G. L. Bourne, R. J. Pawelko, R. A. Anderl, D. G. Tuggle, H. R. Maltrud
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 14-18
doi.org/10.13182/FST95-A11963799
Articles are hosted by Taylor and Francis Online.
A zirconium alloy getter-based tritium monitoring and collection system has been designed, built, and subsequently operated for three years at the Idaho National Engineering Laboratory. The system is automated to provide separation of tritium from 41Ar, collection of tritium on an hourly basis, unloading of getters for on-line tritium measurement via an ion chamber, and recollection of tritium on removable getters for daily assay in the laboratory. Three different SAES Getters alloys are employed to purify the gas stream (St 909), and separate the tritium from Ar and collect the tritium for measurement (St 727 and St 707). This system has demonstrated on-line tritium measurements as low as 20 μCi per sample with typical decontamination factors from 41Ar of 107. In addition, laboratory studies aimed at the recovery of tritium from graphitic targets have demonstrated further process applications for these getters. Prototypical gas cooled reactor targets, containing encapsulated 6Li, were irradiated at the Advanced Test Reactor at this laboratory. Samples were then heated to high temperatures to allow diffusive release of the tritium into a flowing helium stream. St 909 purifier and St 727 collector getters have been employed to demonstrate an efficient tritium recovery process.