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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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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.
J. P. Lestone, A. Gavron
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 213-217
Technical Paper | doi.org/10.13182/NSE94-A19814
Articles are hosted by Taylor and Francis Online.
A statistical model is used with parameters obtained by fitting 232U(n,f) through 236U(n,f) and 238U(n,f) cross-section data to determine the 237U(n,f) fission cross section in the neutron energy range of 0.5 to 20 MeV. Below an incoming neutron energy of 0.5 MeV, the cross section is extrapolated using the neutron energy dependence of the 235U(n,f) reaction. The calculated values to experimental 237U(n,f) cross-section data are compared, and some adjustments are made to the calculated values to obtain a better fit to the existing data.
