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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.
Yoshiyuki Kataoka, Tadashi Fujii, Michio Murase
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 127-135
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35317
Articles are hosted by Taylor and Francis Online.
To evaluate the heat release characteristics of a primary containment vessel (PCV) external spray (one of the PCV cooling systems utilizing the steel PCV wall as the heat transfer medium), the thermal-hydraulic characteristics of the falling liquid film on the PCV surface have been investigated experimentally. Then, the performance of the PCV external spray cooling system was evaluated using the experimental findings. The following results were obtained: 1. Heat transfer coefficients of the falling liquid film under steady-state conditions were increased as the film flow rate per unit length of the liquid film width increased, and they agreed with Wilke’s correlation within about ±15%. 2. The PCV surface temperature, when preheated up to 150°C, which is the supposed PCV temperature under a severe accident, decreased below 100°C within a few seconds when the PCV external spray was initiated, and boiling on the PCV surface could not be maintained. 3. Heat transfer coefficients of the falling liquid film under transient conditions were higher initially due to the boiling effect; however, they decreased rapidly and approached those under steady-state conditions. 4. The PCV external spray for the conceptually designed PCV could suppress the PCV pressure below the design goal under a severe accident (failure of core cooling under low pressure). The maximum PCV pressure decreased as the spray flow rate increased and as the ratio of the PCV surface covered by the falling liquid film increased.