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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
February 2025
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.
N. T. Kazakovsky, I. A. Abramov, A. I. Vedeneev, M. V. Glagolev, A. A. Selezenev
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 692-695
Technical Paper | Tritium Science and Technology - Properties, Reactions, and Applications | doi.org/10.13182/FST05-A1018
Articles are hosted by Taylor and Francis Online.
A method and a laboratory facility were developed for the purpose of determining inflammation temperature of hydrogen-oxygen gaseous mixtures (HOGM). We have determined the inflammation temperature of HOGM containing the following impurities: Ar, Xe, H2O and tritium within the range of initial gas pressure from 3 to 13 kPa. The results agree well with the available reference and numerical simulation results. The inflammation temperatures of HOGM in the range of initial gas pressure from 2 to 13 kPa increases from 793 to 873 K. Average inflammation temperatures of hydrogen and deuterium mixtures differ no more than 1.6 %. Introduction of inert gases (argon and xenon) into gaseous mixture up to 45 volume percent does not change inflammation temperature significantly. Water introduction (in the range from 2.4 to 25 volume percent) does not cause gaseous mixture inflammation. The effect of tritium -radiation on temperature of GM inflammation within the range of tritium concentration concerned is insignificant and agrees with the results of numerical modeling obtained earlier.
