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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.
