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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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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.
Nicholas Chornoboy, Alexandra Levinsky, Charles Kitson, Blair P. Bromley
Nuclear Technology | Volume 204 | Number 1 | October 2018 | Pages 110-118
Technical Note | doi.org/10.1080/00295450.2018.1454229
Articles are hosted by Taylor and Francis Online.
Lattice physics depletion calculations were performed to obtain postburnup fuel compositions for several candidate advanced heavy water reactor fuels. These fuel compositions were used as input for a deep geological repository (DGR) modeling tool for hydrogeology simulations to simulate the transport of radionuclides to the surface, to find the radionuclides that reach the surface path through the biosphere, and to estimate the hypothetical dose rate to humans located above the DGR.
Three primary factors were found to contribute to surface dose rate: burnup, composition of the primary waste matrix, and percentage of thorium in the fuel. Higher burnup and thorium percentage contribute to increased surface dose rates through increased 129I production, while a primarily uranium waste matrix increases surface dose rate through faster dissolution leading to increased radionuclide release rate from the fuel. For all the hypothetical fuels investigated, the estimated dose rates are well within the Nuclear Waste Management Organization’s hypothetical DGR’s acceptance criterion of 0.3 mSv/year.