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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
NRC restores expiration dates for renewed Turkey Point licenses
The Nuclear Regulatory Commission announced this week that it has restored the expiration dates of the Turkey Point nuclear power plant's units 3 and 4 subsequent license renewals (SLR) to July 19, 2052, and April 10, 2053, respectively.
Yoshi Hirooka, Haishan Zhou, Naoko Ashikawa, Takeo Muroga, Akio Sagara
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 345-350
Safety, Environment, and Tritium Handling | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-514
Articles are hosted by Taylor and Francis Online.
The first wall of a magnetic fusion power reactor is defined essentially as the plasma-facing walls of blankets. For the high temperature operation of self-cooled breeder blankets, the first wall is often designed to be less than 1cm thick to reduce mechanical stresses and as a result will be subjected to bi-directional hydrogen permeation by two distinctive mechanisms; in one direction by edge plasma-driven and in the other direction by bred tritium gas-driven permeation. Using a laboratory-scale plasma device and a one-dimensional diffusion model, plasma-driven and gas-driven hydrogen permeation behavior has been investigated under some of the conditions relevant to FLiBe-employed blankets. For a 5mm F82H membrane, the plasma-driven permeation flux at ~500 eC and the gas-driven hydrogen permeation flux at ~350 CC have been measured to be of the orders of 1013 H-atoms/cm2/s and 1014 H-atoms/cm2/s, respectively. From these data one predicts that gas-driven permeation could dominate the hydrogen isotope transport through the first wall.