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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand 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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Latest News
Maintaining RIPB in commercial LWRs
The new standard ANSI/ANS-30.3-2022, Light Water Reactor Risk-Informed, Performance-Based Design, has just been issued by the American Nuclear Society. Approved by the American National Standards Institute (ANSI) on July 21, 2022, the standard provides requirements for the incorporation of risk-informed, performance-based (RIPB) principles and methods into the nuclear safety design of commercial light water reactors. The process described in this standard establishes a minimum set of process requirements the designer must follow in order to meet the intent of this standard and appropriately combine deterministic, probabilistic, and performance-based methods during design development.
Yina Zhang, Chao Zhang, Jin Jiang
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 98-106
Technical Paper | Thermal Hydraulics | dx.doi.org/10.13182/NT12-A13330
Articles are hosted by Taylor and Francis Online.
In this study, computational fluid dynamics simulations are carried out to predict the thermal-hydraulic behavior of supercritical fluids in the subchannel of supercritical water-cooled reactor (SCWR) fuel channels. The thermal-hydraulic behavior of supercritical water in triangular array and square array fuel rod bundles is studied numerically. The effects of various parameters including the pitch-to-diameter ratio and Reynolds number on the flow and the heat transfer characteristics are investigated. It is found that the turbulent mixing coefficient of supercritical water in subchannels is strongly dependent on the fluid bulk temperature and pitch-to-diameter ratio in the vicinity of the pseudo-critical point. To have a higher overall turbulent mixing coefficient, a pitch-to-diameter ratio less than 1.2 is recommended for the design of SCWR. The turbulent mixing coefficient correlation for the triangular array rod bundle is developed in this study based on the numerical results. However, the correlation for the mixing coefficient for the square array rod bundle cannot be expressed as a general correlation.
