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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Liu Cheng-An, Wang Tian-Long, Lu Xun
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 876-881
Advanced Reactor | doi.org/10.13182/FST91-A29455
Articles are hosted by Taylor and Francis Online.
With the Tokamak driver parameters that could be chieved round about 2000 in the world, neutronics studies and analyses have been performed to the blanket configurtion and materials and self-shielding effect of group cross section for the commercial Tokamak fusion-fission hybrid reactor. The main concern of the study has been the assessment of the global tritium breeding ratio, the global Pu239 breeding ratio and determinmatton of the total power production. The results show that it's possible to produce 4 tons of Pu239 per year and net electric output of one GWe, that the self-shielding effect is not important for the fast fission blanket.
