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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Pedro Mata, Rafael de la Fuente, Pablo G. Sedano, Juan Serra
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 275-288
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2839
Articles are hosted by Taylor and Francis Online.
The development of a reload transient analysis methodology for Cofrentes nuclear power plant is presented based on the RETRAN-03 code. The starting point of this methodology was the Cofrentes best-estimate RETRAN model, which had been benchmarked against a number of startup and operational transients. In addition, the best-estimate model had been used to support plant operation and to analyze actual operational and abnormal transients.A number of sensitivity studies have been carried out with the best-estimate model to analyze the effect of the uncertainty associated with the key parameters on the critical power ratio in the most limiting Cofrentes reload transients. The individual uncertainties of key parameters have been combined to obtain the change in critical power ratio (CPR) with a 95% probability level (CPR95).Finally, the Cofrentes licensing model has been defined using conservative values for some significant parameters with the criterion that the calculated CPR cover CPR95. The results obtained with the licensing model have been checked against vendor calculations for the licensing reload transients.This methodology has been submitted to the Spanish Regulatory Commission, and it is expected to be used for the next Cofrentes reload licensing analysis.