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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
William F. Brehm, Robert L. Simons
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 148-155
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34552
Articles are hosted by Taylor and Francis Online.
Measurement of corrosion product radiation levels in the Fast Flux Test Facility heat transport system cells shows a buildup of just over 10 mrem/h in regions near the hot leg and >400 mrem/h near the cold leg. These levels are due to 54Mn only; mere traces of 60Co are observed. The basis for the model used to predict radiation level buildup is reviewed. The observed radiation levels and the predicted values are compared. Discrepancies and reasons for the discrepancies are noted and explained. Some possible changes in calculation methods to increase accuracy in future predictions are presented.
