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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
S. Chatzidakis, A. Ikonomopoulos, S. E. Day
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 119-131
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13332
Articles are hosted by Taylor and Francis Online.
This study presents numerical modeling of the SPERT-IV D-12/25 tests, a series of reactivity insertion, self-limiting, transients for a variety of coolant flow conditions. The PARET-ANL code is used to simulate the system response under these reactivity-initiated accident conditions and estimate the measured damage-indicating parameters - including the cladding temperature - using three departure from nucleate boiling (DNB) correlations, namely, those of Tong, Mirshak, and Bernath. The main objective of this sensitivity analysis is to identify, through performance measures, the DNB correlation influence on the prediction of the transient behavior. It appears that for reactivity insertions >1.20 $, the predicted transient behavior varies significantly depending on the applied DNB correlation. In addition, this study discusses the degree of conservatism introduced by each DNB correlation in the peak clad temperature estimates.
