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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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
Wyoming as a hub for new nuclear manufacturing and microreactor deployment?
A 60-year-old Wyoming industrial machinery company is partnering with nuclear innovator BWX Technologies to deploy 50-megawatt microreactors in America’s heartland over the coming years to provide carbon-free heat and power for industrial users.
Songtao Wu, Weiyue Wu, Yinnian Pan, Damao Yao, Ziying Liao, Yanfang Bi, Zhuoming Chen, Baozeng Li, Yuntao Song, Wenge Chen, Jin Fang, Peide Weng, Daming Gao, Jiangang Li, Yuanxi Wan, Honqiang Li, Wanjiang Pan, Junling Chen, Jing Wei
Fusion Science and Technology | Volume 42 | Number 1 | July 2002 | Pages 146-154
Technical Paper | doi.org/10.13182/FST02-A222
Articles are hosted by Taylor and Francis Online.
The HT-7U superconducting (SC) tokamak will have a long-pulse capability, a flexible poloidal field (PF) system, and auxiliary heating and current drive systems, and it will be able to accommodate divertor heat loads that make it an attractive test for the development of advanced tokamak operating modes. The greatest progress has been made on the engineering design of the HT-7U SC tokamak device, including the calculation and simulation of plasma shaping and control of the PF system as well as calculation and analyses of stress and deformation distribution on the main components caused by dynamic electromagnetic forces, vacuum pressure, temperature differences, etc. Significant research and development progress on the design and the testing of the cable-in-conduit conductor of the toroidal field and PF has been made. A test facility system for the SC magnets of HT-7U has been set up and operated.