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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
J. C. Rook, K. P. Weber, E. C. Corcoran
Nuclear Technology | Volume 206 | Number 12 | December 2020 | Pages 1861-1874
Technical Paper | doi.org/10.1080/00295450.2020.1720557
Articles are hosted by Taylor and Francis Online.
For irradiation experiments (e.g., of per- and polyfluoroalkyl substances), values of nuclear particle flux and absorbed dose rates were obtained for the Safe LOW-POwer Kritical Experiment-2 (SLOWPOKE-2) nuclear reactor at the Royal Military College of Canada using extensive simulations of the reactor core via the Monte Carlo N-Particle code, version 6 (MCNP6). Calculations from this work were compared to data from previously conducted experimental and simulation work to ensure simulation fidelity. In addition, reactor core burnup calculations were conducted using the fuel-depletion capability in MCNP6.1 to address the 30+ years of SLOWPOKE-2 reactor use. The combined absorbed dose rate in the inner irradiation sites was simulated to be 36 ± 1 kGy h−1 at a 10-kW(thermal) power setting, specifically, 20 ± 6 kGy h−1 from neutrons and 16 ± 5 kGy h−1 from photons.