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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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 begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
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.
