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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
A. Labarile, C. Mesado, R. Miró, G. Verdú
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1675-1684
Technical Paper | doi.org/10.1080/00295450.2019.1631051
Articles are hosted by Taylor and Francis Online.
One of the challenges of studying the neutronics of reactors is to generate reliable parameterized libraries that contain information to simulate the core in all possible operational and transient conditions. These libraries must include tables of cross sections and other neutronic and kinetic parameters and are obtained by simulating all the segments in a transport code. At the lattice level, one can use branch calculations to change “instantaneously” the feedback parameters as a function of burnup. When using random sampling for the lattice calculations, one can obtain statistical information about the output parameters and use it in a core simulation to characterize the accuracy of data estimating uncertainties when simulating a heterogeneous system at different scales of detail.
This work presents the methodology to generate NEMTAB libraries from data obtained in the SCALE code system to be used in PARCS simulations. The code TXT2NTAB is used to reorder the cross-section tables in NEMTAB format and generate another NEMTAB of standard deviation. With these libraries, the authors perform a steady-state calculation for a light water reactor to propagate several uncertainties at the core level. The methodology allows obtaining statistical information of the most important output parameters: multiplication factor keff, axial power peak Pz, and axial peak node Nz.