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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
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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
ANS Standards Committee publishes joint ASME/ANS standard for Level 1/large early release frequency PRA
ANSI/ASME/ANS RA-S-1.1-2024, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, has been published by the American Nuclear Society. The document, which is a joint standard developed with the American Society of Mechanical Engineers by the ANS/ASME Joint Committee on Nuclear Risk Management, received the approval of the American National Standards Institute on February 29, 2024, and was issued on March 15, 2024.
Chongyang He, Cong Wang, Yong Liu, Lei Chen, Kun Zhang, Fujun Gou, Songlin Liu
Fusion Science and Technology | Volume 79 | Number 6 | August 2023 | Pages 723-733
Research Article | doi.org/10.1080/15361055.2023.2181045
Articles are hosted by Taylor and Francis Online.
The lithium titanate (Li2TiO3) ceramic pebble bed is one of the main tritium breeder candidates in the solid blankets of fusion reactors. Under the extreme operating conditions of fusion blankets, such as neutron irradiation, high temperatures, structural material extrusion, and stress concentration, the mechanical characteristics of tritium breeding pebble beds not only affect the mechanical performance of the blanket but also affect tritium production and extraction. Therefore, an experimental apparatus was built to characterize the mechanical behavior of 0.47 and 0.99 mm Li2TiO3 pebble beds. A uniaxial compression test was performed under the cyclic mechanical loads of 4, 6, and 8 MPa, respectively. It was shown that large irreversible residual strain appeared in the Li2TiO3 pebble bed with the increase of loading cycles and that the mechanical characteristics of the pebble beds were greatly affected by different mechanical loads and particle sizes. The current results provide relevant experimental data that can support the design of fusion blankets.