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Division Spotlight
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.
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 Science and Engineering
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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.
Takayuki Terai, Akihiro Suzuki, Satoru Tanaka
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 768-772
Chamber Technology | doi.org/10.13182/FST01-A11963331
Articles are hosted by Taylor and Francis Online.
Tritium release behavior from Flibe (Li2BeF4) a potential liquid tritium breeding material was investigated. The main chemical form of tritium-containing species in Flibe was controlled to HT or TF by H2 partial pressure and F− potential in an in-pile experimental system. The release rate coefficients of HT and HF, and HT / TF ratio in released tritium under various H2 partial pressure were observed. The mechanism in chemistry change was considered by a model assuming an isotopic exchange reaction. Increase of HT release rate was observed by the addition of Be metal into Flibe. HT permeation rate coefficient through Monel Metal and SUS316 tubing wall contacting with Flibe were smaller by one order of magnitude than HT release rate coefficient.
