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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.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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.
John D. Burtt, Louis M. Shotkin, Joseph L. Staudenmeier
Nuclear Technology | Volume 119 | Number 3 | September 1997 | Pages 244-268
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35401
Articles are hosted by Taylor and Francis Online.
Calculations were performed for the same accident scenario in the same power plant geometry using the same version of the RELAP5/MOD3.2 computer code, but each calculation was performed using different user options in the code input deck. The accident scenario analyzed was a 1-in. cold-leg break in the new Westing-house AP600 design. The calculations were analyzed for those key events leading to actuation of the AP600 automatic depressurization system. Three different user choices for plant system noding were used: (a) a detailed noding with a quasi-three-dimensional vessel; (b) a simplified system noding with a quasi-three-dimensional core, lower plenum, and upper plenum, but a simplified downcomer noding; and (c) a detailed system and downcomer noding, but a one-dimensional core, lower plenum, and upper plenum. Two other user options were separately exercised, i.e., shutting off the model for thermal stratification and using different initial temperatures for the core. The discussion focuses on the relative effect of these different user options on flow through the P-loop hot leg, initial reversal in flow through the pressure balance line, timing of draining of the core makeup tanks, and timing of actuation of the automatic depressurization system.