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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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
W. C. Redman, M. M. Bretscher
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 247-253
Technical Paper | doi.org/10.13182/NSE68-A18237
Articles are hosted by Taylor and Francis Online.
A combination of relative reactivity measurements and absolute counting techniques has been applied to determine the epicadmium capture-to-fission ratio for 235U. Significant features of this procedure are its requirement of only a moderate neutron flux, the application of 252Cf and manganese to measure the relative importance of fission and absorbed neutrons, and the use of methods that differ from those applied in the high fluence procedures for α measurements. The resulting value of 0.519 ± 0.023, for infinite sample dilution, l/E spectrum, and 0.5-eV low-energy cutoff, is in good agreement with recent results from high fluence irradiations and differential cross-section data.
