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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
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.
