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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.
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.
Sadao Uchikawa, Tsutomu Okubo, Yoshihiro Nakano
Nuclear Technology | Volume 172 | Number 2 | November 2010 | Pages 132-142
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT10-A10900
Articles are hosted by Taylor and Francis Online.
The FLWR is a boiling water reactor type with a core consisting of hexagonal-shaped fuel assemblies with a triangular-lattice fuel rod configuration, which has been proposed in order to ensure a sustainable energy supply in the future based on well-established light water reactor technologies. This paper proposes a new concept of fuel assembly design named FLWR/MIX. The first stage of FLWR is designed to conserve plutonium effectively with a fissile plutonium conversion ratio of around 1.0, keeping negative void reactivity characteristics. Enriched UO2 fuel rods are arranged in the peripheral region of the assembly, surrounding the mixed oxide (MOX) fuel rods in the central region. Performance evaluation shows that the FLWR/MIX concept is effective for controlling the void reactivity characteristics in the tight-lattice fuel rod configuration and is promising under the framework of the UO2 and MOX fuel technologies and related infrastructures that have been established for the current LWR-MOX utilization.