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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
C. Vaglio-Gaudard, A. Santamarina, P. Blaise, O. Litaize, A. Lyoussi, G. Noguère, J. M. Ruggieri, J. F. Vidal
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 89-106
Technical Paper | doi.org/10.13182/NSE09-91
Articles are hosted by Taylor and Francis Online.
The Programme d'Etude du Réflecteur Lourd dans Eole (PERLE) critical experiment was recently performed in the EOLE zero-power reactor to provide representative experimental data for heavy stainless steel (SS) reflector physics. It is a UO2 regular 27 × 27 square core surrounded by a 22-cm-thick SS block. The neutron source presents the same spectrum as Gen-III pressurized water reactors (PWRs).The analysis of measurements with the TRIPOLI4 reference Monte Carlo calculations notably aims at validating 56Fe nuclear data in the JEFF3.1.1 library. Large uncertainties are still associated with 56Fe nuclear data, in particular for the inelastic cross section ([approximate]10% at 1) since considerable discrepancies have been observed between various international evaluations of the inelastic level.This paper is dedicated to the analysis of the PERLE experiment. The reactivity worth of the PERLE heavy reflector was measured and compared with the efficiency of both the water reflector and the standard PWR reflector (2-cm-SS baffle). The radial power distribution at the core/reflector interface was measured by direct gamma spectrometry on fuel pins. The TRIPOLI4 analysis gives satisfactory results. The flux attenuation with SS penetration was measured by miniature fission chambers and metallic activation foils, using the fast, intermediate, and thermal response function. Interpretation of flux attenuation measurements shows calculation/experiment discrepancies within the experimental uncertainty. These results highlight that the 56Fe cross sections in the JEFF3.1.1 library have been evaluated accurately.