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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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Nuclear Technology
Fusion Science and Technology
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.
Carlos E. Velasquez, Graiciany P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Antonella L. Costa
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 625-629
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-949
Articles are hosted by Taylor and Francis Online.
Different first wall material proposals based on tungsten alloy WNiFe, WLa2O3, W1.1TiC, W26Re, beryllium alloy S-B65, stainless steel SS316 and graphite have been studied in the last years. These materials must be capable of withstanding high temperature and neutron flux. Nevertheless, using hybrid systems, the first wall material choice could influence the criticality system due to the different properties of each material. To analyze this influence, two hybrid reactors were evaluated. The first one is a Tokamak based on magnetic confinement and the second one based on inertial confinement. Both systems contain a transmutation layer with reprocessed fuel spiked with thorium. The results showed the principal nuclides affected in the transmutation layer and the differences in the criticality due to neutron flux variations produced by the changes in the first wall material.