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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Hiroaki Suzuki, Soji Koikari, Seiichi Koshizuka, Derek H. Lister
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 65-77
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14519
Articles are hosted by Taylor and Francis Online.
A modified six-step evaluation procedure has been proposed to evaluate local wall thinning due to flow-accelerated corrosion (FAC). In step 1, the one-dimensional (1-D) distribution of flow turbulence and the temperature along pipes in cooling systems were analyzed with a 1-D system simulation code to obtain approximate mass transfer coefficients at structure surfaces, prior to using a three-dimensional (3-D) computational fluid dynamics (CFD) code for precise flow turbulence analysis of the major parts. In step 2, corrosive conditions were calculated with a N2H4-O2 reaction analysis code. In step 3, high FAC risk zones were determined for further evaluation for wall thinning rates, based on five parameters: temperature, pH, oxygen concentration, mass transfer coefficient, and chromium content. Then, in step 4, the 3-D CFD code was used to calculate precise mass transfer coefficients at the high FAC risk zones. In step 5, the wall thinning rates were calculated using a coupled model of electrochemical analysis and oxide layer growth analysis by applying the corrosive conditions and the mass transfer coefficients. Finally, in step 6, the residual lifetime of the pipes and the applicability of countermeasures against FAC were evaluated.This paper introduces procedures for determining major FAC parameters and evaluation procedures for high FAC risk zones by synthesizing the parameters in step 3. The procedures for determination of high FAC risk zones in a pressurized water reactor secondary cooling system are also demonstrated.