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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.
J. B. Yang, X. G. Tuo, Z. Li, Y. Cheng, L. Wang, H. H. Wang, B. Cai, M. Z. Liu
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 233-238
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-A22318
Articles are hosted by Taylor and Francis Online.
To improve the yield of online prompt gamma neutron activation analysis, the Monte Carlo N-Particle Transport Code (MCNP) is used to simulate the computation and analysis of the material and thickness of reflectors on both sides of the sample chamber as well as the type and thickness of the neutron-absorbing material in front of the detector. The simulation shows that the optimal thickness of the reflecting material is [approximately]100 mm when heavy water is added on both sides of the sample chamber and the optimal thickness of the neutron-absorbing material is [approximately]50 mm when polyethylene-containing boron is added in front of the detector. The experiment demonstrated that the yield of prompt gamma rays of the main elements in the cement sample increased to some extent.
