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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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.
Theo G. Theofanous, Hongfei Yan
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 332-353
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34793
Articles are hosted by Taylor and Francis Online.
This is the second part of a three-part series of papers addressing the probability of liner failure in a Mark-I containment. The purpose is to quantify melt release and spreading phenomena in a form suitable for use in the probabilistic framework as discussed in the first part of this series. The quantification of melt release parameters (quantity, superheat, and zirconium content) is derived from an assessment of available system code results and certain independent auxiliary considerations of the physics of the meltdown and slumping processes in the relevant geometries. The quantification of melt spreading phenomena is based primarily on simulant scaled experiments run specifically for this purpose; however, auxiliary considerations of the physics of operative cooling and quenching mechanisms also play a significant role in this assessment.