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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Francesco Ghezzi, Walter T. Shmayda, Giovanni Bonizzoni
Fusion Science and Technology | Volume 31 | Number 1 | January 1997 | Pages 75-105
Technical Paper | Tritium System | doi.org/10.13182/FST97-A30781
Articles are hosted by Taylor and Francis Online.
Tritium gas handling involves the production of tritiated water, which is 10000 times more hazardous than tritium gas. If tritium emission to the environment must be minimized, the need to process tritiated water and recover the chemically bound tritium appears clear. Facilities for processing tritiated water produced in fission reactors are already available, while facilities for a deuterium-tritium fusion machine are under development. However, these facilities are intended for large-scale applications and are neither practical nor economical for small-scale applications. HTO vapor reduction to HT over a hot metal getter other than uranium offers a simple, safe, and economical solution. A high alloy capacity and conversion rate combined with a low tritium residual inventory in the exhausted alloy make this method attractive. An experimental investigation of the efficiency of reducing HTO by a Zr-Fe-Mn alloy is presented. The results, obtained by three independent diagnostics (stripper set, ionization chambers, and mass spectrometry), show that for gas residence times >1 s and alloy temperatures >400°C, a conversion efficiency exceeding 90% is achievable. Specific conversion rates >0.1 μmol/s·g−1 are observed during the alloy usage, while a capacity of the alloy, measured as an oxygen-to-alloy mole ratio, >2.6 has been measured.