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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.”
James T. Cronin, Kord S. Smith
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 174-183
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34740
Articles are hosted by Taylor and Francis Online.
A methodology for homogenization and functionalization of one-dimensional cross sections for RETRAN has been developed and encoded into the SIMULATES and SLICK computer programs. The method relies on the SIMULATE-3 nodal reactor analysis code to provide accurate solutions of the three-dimensional neutron diffusion equation in two energy groups. The process of producing the required data involves two distinct problems: (a) the spatial homogenization of the three-dimensional cross sections and diffusion coefficients into one-dimensional variables and (b) the functionalization of the one-dimensional data in terms of the feedback variables of coolant density, fuel temperature, and control fraction. The homogenization method is based on equivalence theory and preserves the eigenvalue and one-dimensional planar reaction rates of the three-dimensional solution. The functionalization of the homogenized cross sections is accomplished by performing analogous one-dimensional state calculations with the RETRAN thermal-hydraulic models and then fitting to the RETRAN feedback variables. The methodology has been verified by comparing the results of one-dimensional calculations performed with the one-dimensional cross sections to three-dimensional calculations. Close agreement between the one- and three-dimensional results has been demonstrated.