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Division Spotlight
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.
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.
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.