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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
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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.
H. Oka, M. Nishikawa, T. Takeishi, J. Yamaguchi, M. Nishi, T. Hayashi, K. Kobayashi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 658-662
Safety and Safety System | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22669
Articles are hosted by Taylor and Francis Online.
The system effect of tritium arises from the interaction of tritium in the gas phase with water on the surface of piping materials. It has been reported that the system effect can be quantified by applying the serial reactor model to the piping system, connection of perfect mixed flow type reactors and plug flow type reactors, and that adsorption and isotope exchange reactions play the main roles in the trapping of tritium. In this study we made a calculation code of the system effect using the serial reactor model where 304SS, aluminum, copper or graphite is used for the piping material. Comparison of the calculated value using this code gives the good agreement with the experimental data taken at the cooperative experiment using a box made of stainless steel type 304 in Tritium Processing Laboratory in JAERI and that is called as the Caisson. It is observed that the isotope exchange reaction between tritiated water in the air and surface water on the 304SS surface controls the tritium trapping performance at the room temperature although HTO/HT ratio is around 0.1 in this experiment.