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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.
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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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February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Yung Sung Cheng, Yue Zhou, Charles A. Gentile, Charles H. Skinner
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 867-871
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22708
Articles are hosted by Taylor and Francis Online.
Amorphous tritiated carbon films are formed through co-deposition of the radioactive isotope tritium (3H or T) with carbon onto plasma facing surfaces in fusion plasmas. The Tokamak Fusion Test Reactor (TFTR), operated by the Princeton Plasma Physics Laboratory, was fueled by tritium and deuterium neutral beam injection and gas puffing. Tritium was co-deposited as amorphous hydrogenated carbon onto graphite tiles and stainless steel surfaces inside the reactor. Since termination of plasma operations, carbon tritide particles have remained in the air in the vessel. Dosimetric limits for occupational exposure to carbon tritide particles need to be established. The purpose of this study was to characterize carbon tritide particle samples inside the TFTR in terms of size, self-absorption of tritium beta, and dissolution rate in simulated lung fluid. Dose estimates of the inhaled carbon tritide particles can be calculated based on the dissolution rate, particle size, and self-absorption factor. The count median diameter and geometric standard deviation were 1.23 µm and 1.72, respectively, indicating that they are respirable particles and can stay suspended in the air for a longer time. The dissolution rate in the lung-simulated fluid was determined in a static system. The dissolution rate ranged from 10−1–10−3 per day in the first few hours, then it decreased to between 10−3 and 10−4. The retention curve of tritium in carbon indicated that >90% of the tritium remained in the particles after 110 d in the simulated lung fluid. This information is being used to support the establishment of respiratory protection requirements.