ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Ming Zhi Huang, Chong Zhou, Pu Yang, Wei Shi Wan, Zuo Kang Lin, Ye Dai
Nuclear Technology | Volume 209 | Number 1 | January 2023 | Pages 15-36
Technical Paper | doi.org/10.1080/00295450.2022.2096390
Articles are hosted by Taylor and Francis Online.
The existing thermal neutron molten salt reactor design has a complicated online processing system that has many technical difficulties. A thorium-based molten salt fast energy amplifier (TMSFEA) driven by a proton accelerator can operate stably for nearly 40 years at a rated thermal power of 300 MW without online processing. In order to simplify the core structure of TMSFEA, the core design is based on a hollow and moderator-free cylindrical geometry. The molten salt in the core serves as both fuel salt and spallation target. In this paper, based on the previous TMSFEA core neutron physics design, the core thermal-hydraulic design principles of TMSFEA are proposed, and a detailed core design with specific core structures as well as three-dimensional core thermal-hydraulic performance are obtained. Through computational fluid dynamics steady-state analysis, the arrangement of the core inlet and outlet and the shape of the core sidewall are optimized. Suitable distribution plates and skirt plates are proposed, and two corresponding lower plenum structures are designed to improve the flow field in the core. This study provides TMSFEA with core structures that meet the thermal-hydraulic design principles and also provides ideas for similar hollow reactor core designs.