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
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
R. B. Kidman, R. E. Schenter, R. W. Hardie, W. W. Little
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 189-201
Technical Paper | doi.org/10.13182/NSE72-A22470
Articles are hosted by Taylor and Francis Online.
The essential features of the shielding factor method of computing effective multigroup cross sections are presented. This includes both the generation of shielding factors and infinitely dilute cross sections from the ENDF/B data, and the use of these constants in computing effective multigroup cross sections. Representative numerical results comparing the shielding factor method with another, more detailed, cross-section generation technique are also included.