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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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Hiroaki Suzuki, Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Souji Koikari, Yukihiko Nagaya, Akira Nakamura, Seiichi Koshizuka, Derek H. Lister
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 62-74
Technical Paper | Thermal Hydraulics/Materials for Nuclear Systems | doi.org/10.13182/NT13-A16992
Articles are hosted by Taylor and Francis Online.
A six-step procedure based on three-dimensional (3-D) computational fluid dynamics codes and a coupled model of electrochemistry and oxide layer growth models was proposed to estimate local wall thinning due to flow-accelerated corrosion (FAC), and they were applied to evaluate wall-thinning rates, residual lifetimes of the pipes, and applicability of countermeasures against FAC. A verification and validation (V&V) evaluation based on a comparison of calculated and measured wall thinning confirmed that the wall-thinning rate could be predicted with an accuracy within a factor of 2 and that residual wall thicknesses after 1 year of operation could be estimated with an error of <20%.To mitigate one of the disadvantages of the 3-D FAC code, which is the large amount of computational time needed, and to evaluate FAC occurrence probability for entire plant systems, a one-dimensional (1-D) FAC code was developed by applying 1-D mass transfer coefficients and geometrical factors. High-FAC occurrence zones along entire cooling systems and the effects of countermeasures on mitigating the risks could be evaluated within a small amount of computer time. Prior to application of the easy-to-handle FAC code for plant analysis, its accuracy and applicability should be confirmed based on V&V processes. From comparison of maximum wall-thinning rates calculated with the 1-D FAC code, those calculated with the 3-D FAC code, and measured results for experimental loops and secondary piping of an actual pressurized water reactor plant, it was confirmed that the calculated wall-thinning rates agreed with the measured ones within a factor of 2.