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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.
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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.
Tomohiro Endo, Akio Yamamoto
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1089-1104
Technical Paper | doi.org/10.1080/00295639.2020.1720499
Articles are hosted by Taylor and Francis Online.
The prompt neutron decay constant in a steady-state subcritical system can be directly measured using a reactor noise analysis method such as the Feynman- method. To reduce the nuclear data–induced uncertainty of for a target system, this study investigates the applicability of data assimilation techniques, i.e., the bias factor method and the cross-section adjustment method, based on a subcritical measurement of conducted at Kyoto University Critical Assembly (KUCA). The sensitivity coefficients of and with respect to the nuclear data were efficiently estimated using a deterministic SN transport code with first-order perturbation theory. As a result, the a priori relative uncertainty of due to the 56-group SCALE covariance data can be reduced if there is strong correlation between the measured and the target . The experimental value of contributes to improving the nuclear data of total fission spectrum and total fission neutron number via strong correlations between and prompt and between and prompt , by utilizing the sensitivity coefficients of with respect to prompt and .