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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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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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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.
Jong-Won Kim, Jong-Soo Choi, Young-In Kim, Young-Jong Chung, Goon-Cherl Park
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 336-351
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13479
Articles are hosted by Taylor and Francis Online.
SMART (System-integrated Modular Advanced ReacTor) is an integral-type nuclear reactor for cogeneration that adopts a flow mixing header assembly (FMHA) to maintain a uniform temperature distribution in the coolant at the core inlet in the case of failure in the steam generator or reactor coolant pump. The SMART FMHA is important for enhancing thermal mixing of the coolant during a transient and even during accidents, so it is essential that the thermal-hydraulic characteristics of flow in the FMHA be understood. Scaling analysis was performed to design the experimental facility for the FMHA test through computational fluid dynamics (CFD) analysis on the SMART prototype and experimental model. The experimental facility was designed by a linear scaling factor 0.18, and the experimental pressure and temperature conditions were 0.1 MPa and 30°C to 60°C, respectively.The experiment was performed in two ways: using FMHAs with large outlet flow hole sizes and FMHAs with small outlet flow hole sizes. In the cases of failure of one or two steam generators, the maximum temperature deviation on the side of the reactor core inlet was measured to be 1°C to 2°C, which demonstrates excellent thermal mixing through the FMHA. In particular, the FMHA with small outlet flow hole sizes tended to have better thermal mixing than the FMHA with large outlet flow hole sizes. The experimental results were comparable to those from CFD analysis.