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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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2025 ANS Annual Conference
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Chicago, IL|Chicago Marriott Downtown
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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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WMG FLTRSTOR™ System Overview
WMG’s FLTRSTOR™ system provides a proven, practical solution for the efficient handling, storage, and shipment of irradiated filters and velocity limiters (VLs) in support of nuclear plant operations. With successful implementations at many sites, the system is recognized for saving time, reducing personnel dose, and cutting overall waste handling costs. Our satisfied and returning FLTRSTOR™ customers include:
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.