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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
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Yican Wu, Qunying Huang, Zhiqiang Zhu, Sheng Gao, Yong Song
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 272-275
Fusion Technology Facilities | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14146
Articles are hosted by Taylor and Francis Online.
The liquid LiPb blanket concept has become a promising design for fusion reactor in the world, and a series of fusion reactors with LiPb blankets have been designed by FDS team in China. To support the various designs and technologies of Chinese LiPb breeder blankets, LiPb experimental loops have been built to follow the different phases of LiPb blankets requirements and to achieve different testing functions. Three thermal convection loops named DRAGON-I, II, and III were built to carry out the compatibility experiments and validate the loop technology, and the multifunctional forced convection loops named DRAGON-IV and V were built or designed to validate the magnetohydrodynamic effect and thermal-hydraulics test. Three sets of He-LiPb dual-coolant auxiliary systems named DRAGON-VI, VII, and VIII were designed and proposed for testing test blanket modules in EAST, ITER, and DEMO blankets in the future. An overview on the design and construction of these loops is introduced in this paper, as well as some preliminary experiments done in the loops.