ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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 Technology
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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.
Z. F. Kuang, I. Pázsit
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 305-319
Technical Note | doi.org/10.13182/NSE00-A2161
Articles are hosted by Taylor and Francis Online.
Recently, analytical formulas have been derived for the Feynman- and Rossi-Alpha measurements in accelerator-driven systems. In such systems, due to the multiplicity of the sources, the Feynman- and Rossi-Alpha formulas contain additional terms as compared with the traditional cases. A numerical evaluation of these formulas for systems with such sources is given. An assessment of the contribution of the terms that are novel as compared to the traditional formula is made. These include the terms arising from the source multiplicity, and the prompt-delayed and delayed-delayed correlations. Further, the consequences of averaging the delayed-neutron families are analyzed. Finally, a comparison is made, assuming traditional core material and one possible type of future accelerator-driven system.