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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Hermann Würz
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 193-206
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34556
Articles are hosted by Taylor and Francis Online.
A method for nondestructive assay of spent light water reactor fuel assemblies based on a combination of active and passive neutron counting is presented. After geometrical optimization, the Fuel Assembly Monitoring System (FAMOS) is a rather simple system. It allows the burnup, initial enrichment, type of fuel (uranium or mixed oxide), and criticality of the spent-fuel assembly to be determined. The results of a characterization program with emphasis on boiling water reactor (BWR) fuel assemblies are discussed. Burnup-dependent neutron emission data for spent BWR fuel are now available. The effect of steam void on plutonium and curium buildup is demonstrated. Because of this effect, the axial measurement position is of importance for an accurate assay. If the measurement is done at the upper part of the BWR fuel assembly, the error in burnup remains below ±2 GWd/tonne U, and the initial enrichment can be determined with an accuracy of ±15%. This still allows a clear distinction between the different enrichment regions used for BWR fuel assemblies.