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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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.
Karen A. Miller, Martyn T. Swinhoe, Stephen Croft, Takayuki Tamura, Shun Aiuchi, Akio Kawai, Tomonori Iwamoto
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 98-105
Technical Paper | doi.org/10.13182/NSE12-43
Articles are hosted by Taylor and Francis Online.
As new uranium enrichment plants are proposed and come online worldwide, interest in using neutron methods for uranium hexafluoride (UF6) cylinder assay has been growing; however, large discrepancies exist in published F(α,n) yields from uranium isotopes. Uncertainties in these data are propagated through the analysis of every UF6 measurement and have implications for safeguards conclusions drawn from them. In this paper, a value for the specific F(α,n) yield in UF6 from 234U is calculated from measurements of 30B cylinders containing bulk UF6 at the Rokkasho Enrichment Plant in Japan. The measurements were taken using the Uranium Cylinder Assay System. The yield was derived by combining the cylinder measurements with detailed Monte Carlo modeling, known isotopic composition, and inversion analysis. We calculated the 234U neutron emission rate in UF6 to be (474 ± 21) n/s·g−1 with a 68% confidence level. The results obtained in this study will help enable an important class of nondestructive assay instruments to be applied with greater confidence and accuracy.
