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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Yafen Liu, Rui Yan, Yang Zou, Xuzhong Kang, Ruimin Ji, Bo Zhou, Shihe Yu
Nuclear Technology | Volume 204 | Number 2 | November 2018 | Pages 203-212
Technical Paper | doi.org/10.1080/00295450.2018.1474703
Articles are hosted by Taylor and Francis Online.
Zero-power experiments are very important parts in design verification for all reactor types. In the 1970s, in China, at the Shanghai Institute of Applied Physics (then, Shanghai Institute of Nuclear Research), a Critical Experiment Device (cold) was established for research on the physics characteristics of the molten salt reactor (MSR), and a series of zero-power experiments was successfully performed; related experimental results were obtained later. The device consisted mainly of graphite moderator and powdered BeF2 – UF4 / ThF4 fuel and could achieve a maximum power of 200 W. The current work is focused on criticality properties with various core configurations and fuel arrangements of this device and the worths of the cadmium rods used in the device. Evaluations on the agreement of calculation results with experimental data showed good results. Discrepancies between the calculation results and the experimental data might be primarily caused by the simulated outermost fuel element positions not being exactly the same as the experimental arrangements and the unmodeled instruments used in the experiments. The findings in this work can be considered a step of verification of simulation methods and calculations for a cold MSR.