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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Robert P. Schuman
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 422-431
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33398
Articles are hosted by Taylor and Francis Online.
Two leach-resistant waste forms, a borosilicate glass developed for the high-level waste calcines from reprocessed uranium fuels and iron-enriched basalt, a fused ceramic developed for americium plus plutonium wastes, have been leach tested. The specimens were leached in distilled deionized water and in a saturated salt brine at ∼30°C for 28, 63, and 126 days; one set was leached in a gamma field of ∼104 Gy/h (∼106 rad/h). The specimens were simulated high-level waste forms prepared from inactive ingredients and spiked with 22Na, 60Co, 95Zr-95Nb, 137Cs, 133Ba, 144Ce, and 241Am. The components were melted and heat treated, and specimens were sawed from the solidified material. The gamma field increased the leach rates in water (pH ∼3 after irradiation) typically by a factor of ∼10 and increased the leach rates in salt brine (pH decreased much less during irradiation) by a factor of ∼2. The leach rate of cobalt from glass was about seven times that from iron-enriched basalt. The leach rates usually decreased with increasing leach time. Both waste forms were still leach resistant in irradiated brine at 30°C, <2 µg/cm2·day, and fairly leach resistant in irradiated water at 30°C, <25 µg/cm2·day.