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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
F. Masse, C. Latge
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1039-1044
Analysis and Accountancy | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30543
Articles are hosted by Taylor and Francis Online.
One of the critical issues in the development of Breeding Blankets for the Fusion Demonstration Reactor, DEMO, is the tritium control, particularly in the coolant and the tritium extraction system. To be able to understand and model the tritium behaviour and releases through various interfaces, a code is being developed, following the same approach as for Liquid Metal Fast Breeder Reactors (LMFBRs) for which an efficient tool is already available: KUTIM, here described The new model proposed for fusion purposes will contribute to compare and choose means to reduce the tritium releases and more generally will be a support for design activities for Breeding Blankets.