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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Ontario eyes new nuclear development
A 1,300-acre site left undeveloped on the shores of Lake Ontario four decades ago could see new life as the home to a large nuclear facility.
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.