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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Kenjiro Matsuhiro, Hirofumi Nakamura, Takumi Hayashi, Hiroo Nakamura, Masayoshi Sugimoto
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 625-628
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A1003
Articles are hosted by Taylor and Francis Online.
In International Fusion Material Irradiation Facility (IFMIF), neutrons are produced by the reaction between 40 MeV deuterium and liquid lithium. In this process, tritium (3 × 1011 Bq/h) is generated in the lithium flow. Tritium permeation and inventory of IFMIF lithium loop components are evaluated for safety of the IFMIF and the design of tritium processing system of the IFMIF. The tritium permeation rate from a V-Ti hot trap is about 95% of the total amount, 1.0 × 106 Bq/h, from lithium loop. Therefore, the reduction of the tritium permeation rate from only the V-Ti hot trap can directly reduce the total tritium permeation from the Li loop and the gaseous tritium in the Li loop area. Total tritium contained in the walls ewt by liquid lithium in the IFMIF is 5.3 × 107 Bq, which is much smaller than 4.9 × 1014 Bq of tritium contained in the Li flow with a volume of 9 m3.