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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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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.
Kou-John Hong, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 80 | Number 4 | April 1982 | Pages 570-578
Technical Paper | doi.org/10.13182/NSE82-A18970
Articles are hosted by Taylor and Francis Online.
For transport problems with fine energy group structure, the group-to-group transfer, cross sections are usually quite anisotropic in the scattering angle. It is shown for neutron inelastic scattering that explicit use of the characteristic shape of these transfer cross sections permits more efficient and accurate numerical evaluation of their Legendre expansion coefficients than is afforded by existing techniques. In addition, transfer cross sections can often be well approximated by piecewise, low-order polynomials with which very accurate and simple expressions can be derived for the Legendre coefficients. This analytical approach both minimizes the access of nuclear data files and accurately determines even the higher order coefficients.