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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Mahmoud Z. Youssef
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1552-1567
Neutronic and Shielding | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A39984
Articles are hosted by Taylor and Francis Online.
Described are procedures to be followed in applying cross-section sensitivity and uncertainty analysis to arrive at estimates for the uncertainty associated with an integrated reactor performance parameter R. Means to reduce such uncertainty are outlined. The pertaining computational codes used as analytical tools to carry out the cross-section sensitivity/uncertainty analysis are reviewed with emphasis on their current limitations and possible improvements. The range of the uncertainty in the prediction of the tritium breeding ratio TBR due exclusively to current uncertainties in the nuclear data field is presented as an application for the sensitivity and uncertainty methods and codes.