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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
T. V. Kulsartov, Zh. A. Zaurbekova, I. E. Kenzhina, M. T. Gabdullin, Yu. V. Ponkratov, S. K. Askerbekov, K. K. Kadyrzhanov
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 333-340
Technical Paper | doi.org/10.1080/15361055.2020.1712006
Articles are hosted by Taylor and Francis Online.
This paper describes the procedures for calculating parameters of hydrogen isotopes interaction with materials according to the results of experiments conducted by dynamic sorption methods under conditions of complex exposure. Using the proposed approach, we analyzed the data of reactor tests of a lithium capillary porous system based on a stainless steel matrix conducted under conditions of sample purging with deuterium (at a pressure of deuterium in the chamber ~10–2 to 10–4 Pa). The sample was irradiated at various temperatures (T = 180° to 550°) under conditions of oil-free pumping and with continuous mass spectrometric recording of the gas composition in the chamber.