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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.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
N. D. Dudey, D. Meneghetti, R. R. Heinrich, R. H. Rempert
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 9-26
Technical Paper | doi.org/10.13182/NSE74-A23327
Articles are hosted by Taylor and Francis Online.
Measurements of integral neutron capture-to-fission cross-section ratios and neutron capture rates of 233U, 235U, 238U, 239 Pu, 240 Pu, and 242Pu at 15 radial and axial positions in EBR-n are reported. Fission rates were determined by measurement of the fission product 137Cs and capture rates were determined by mass-spectrometric and alpha-spectrometric analysis. Capture-to-fission ratios at all sample locations and central fission and capture ratios were calculated by two-dimensional RZ and XY geometries using multigroup analyses. Details of geometry and reactor composition changes during the course of the irradiations are considered and found to be significant for the fertile isotopes. A detailed comparison between measurement and calculation is presented and discussed in terms of the calculational model, cross-section data, and experimental uncertainties. Calculations were made using both Versions I and HI of ENDF/B.