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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).
Massimiliano Fratoni, Ehud Greenspan
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 1-16
Technical Paper | doi.org/10.13182/NSE09-66
Articles are hosted by Taylor and Francis Online.
The capability to perform depletion analysis of pebble bed reactors has been traditionally limited to a few dedicated codes that are designed for helium-cooled reactors, rely on pregenerated problem-dependent group cross sections, and have limited flexibility in the materials and in the geometries they can model. This paper presents a newly developed tool to search for pebble bed reactor core equilibrium composition and calculate its neutronic characteristics. It uses MCNP for transport calculations and ORIGEN2 for depletion calculations and can generate effective one-group cross sections “on-the-fly” as pebbles move through the core using point-energy cross sections. This tool can be used for any coolant type including liquid salt, can model complex geometries, and can account for any level of heterogeneity. Also developed are two simplified methodologies that are based on unit-cell analysis and can considerably reduce the required computational time; they are useful for parametric studies.