ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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.
Dermott E. Cullen
Nuclear Science and Engineering | Volume 99 | Number 2 | June 1988 | Pages 172-181
Technical Note | doi.org/10.13182/NSE88-A23557
Articles are hosted by Taylor and Francis Online.
The results of the International Atomic Energy Agency cross-section processing code verification project are described. This project has been conducted over the last 7 yr in an attempt to improve the reliability of the results produced by cross-section processing computer codes. Initial comparisons of results received from 42 participants using 13 different cross-section processing codes demonstrated that, even though all of the codes started from exactly the same evaluated data, in no case did the multigroup cross sections calculated by any two codes agree for all materials and groups used in the comparison. This code verification project has led to positive results by improving cross-section processing codes as well as the conventions used to interpret ENDF/B evaluations. In several cases it has led to changes in ENDF/B evaluations. Although this project only addressed nuclear data processing codes, conclusions can be drawn from the results regarding the reliability of other types of computer codes.