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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Nuclear new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
Wei Xu, Jianhua Xia, Xiaojing Liu, Xu Cheng, Wei Zeng
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 281-296
Technical Paper | doi.org/10.1080/00295450.2018.1457887
Articles are hosted by Taylor and Francis Online.
Bottom reflooding is the third phase when a large-break loss-of-coolant accident occurs. Due to the complexity and importance, especially in a distinct narrow rectangular channel, various research methods can be utilized to understand the whole process. Test facility is established to figure out the thermal-hydraulic behaviors during bottom reflooding, and the acquisition of accurate solid temperature is essential. The inverse heat transfer problem method is applied to take full advantage of experimental data. In addition, a bottom reflooding transient (BRT) code is utilized to calculate various parameters conveniently. A three-dimensional heat conduction equation for a transient state is solved implicitly to obtain solid temperature distribution, surface heat flux, and heat transfer coefficient at the cooling surface. The simulation results of the BRT code are compared with that of RELAP5, an available system code, and the experimental results. A conclusion that can be derived is that the BRT code shows good applicability of simulating bottom reflooding in a narrow rectangular channel.