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.
K. Ilieva, T. Apostolov, S. Belousov, Iv. Penev, I. Popova
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 243-247
Technical Paper | doi.org/10.13182/NSE97-A24271
Articles are hosted by Taylor and Francis Online.
Validation of neutron fluence on VVER-440 pressure vessel methodology is performed by comparative analysis of calculational compared with experimental results for the induced activity of scraps taken out from the inner surface of the VVER reactor pressure vessel after the 14th and 17th cycles. The mean deviation of 9% between the experimental and the calculated activity values is evaluated. The good consistency of the results demonstrates the validity of the neutron fluence calculational methodology.