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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
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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Nuclear Technology
Fusion Science and Technology
Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
D. Demange et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 182-187
Technical Paper | Tritium Science and Technology - Decontamination and Waste | doi.org/10.13182/FST05-A908
Articles are hosted by Taylor and Francis Online.
This work deals with an indirect and non destructive measurement of tritium in solids. Instead of measuring tritium, we propose to measure the production rate of the decay product: 3He.The amount of tritium enclosed inside a waste drum can be determined with an adapted 3He ingrowth method that takes into account the leak rate of the drum. The model leads to different ways to quantify tritium in the drum. It is confirmed using reference drums that measuring the 3He leak by confining the drum during its equilibrium state gives the same result as sampling the drum atmosphere at the beginning of the storage. For each method, the appropriate apparatus, experimental procedures and calculation of tritium activity from mass spectrometric 3He measurements are detailed. Performances of these techniques are studied and discussed.In addition, we describe a novel and fully automated apparatus based on the confinement method that makes it possible to achieve a close tritium inventory of all the waste drums stored or produced at CEA Valduc.