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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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
BWXT announces nuclear manufacturing plant expansion
BWX Technologies announced today plans to expand and add advanced manufacturing equipment to its manufacturing plant in Cambridge, Ontario, Canada.
A $36.3 million USD ($50M CAD) expansion will increase the plant’s size by 25 percent—to 280,000 square feet—and another $21.7 million USD ($30M CAD) will be spent on new equipment to increase and accelerate its output of large nuclear components. The investment will increase capacity and create more than 200 long-term jobs for skilled workers, engineers, and support staff, according to the company.
E. Royer, E. Raimond, D. Caruge
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 154-165
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3381
Articles are hosted by Taylor and Francis Online.
The Organization for Economic Cooperation and Development/Nuclear Energy Agency Main Steam Line Break (MSLB) benchmark provides a comparison of state-of-the-art and best-estimate models used to compute reactivity accidents. A comprehensive study has been carried out by Commissariat à l'Energie Atomique and Institut de Radioprotection et de Sûreté Nucléaire with the CATHARE, CRONOS2, and FLICA4 codes. The effect of mixing between primary loops in the core vessel is analyzed, then zero-dimensional and three-dimensional (3-D) kinetics are compared, and finally, the effect of the core thermal-hydraulic model is presented. The aim of this analysis is to assess the 3-D effects in the MSLB accident and to explain the return-to-power occurrence.