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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.
2021 Student Conference
April 8–10, 2021
North Carolina State University|Raleigh Marriott City Center
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 Science and Engineering
Fusion Science and Technology
Baranwal reviews virtual STEM lessons for U.S. tribal communities
In a blog post to the Department of Energy’s website on November 23, Rita Baranwal, assistant secretary for the Office of Nuclear Energy, commended recent virtual lesson projects from the Office of Nuclear Energy and the Nuclear Energy Tribal Working Group to increase STEM opportunities for Native American tribes.
The spotlighted lesson discussed in the article focused on a 3D-printed clip that turns a smartphone or tablet into a microscope with the ability to magnify items by 100 times. The Office of Nuclear Energy shipped nearly 1,000 of these microscope clips to students across the country, many of them going to U.S. tribal communities.
Songtao Yin, Hongdong Zhen, Lei Zhang, Bo Cheng, Ningning Wang, Haijun Wang
Nuclear Science and Engineering | Volume 193 | Number 12 | December 2019 | Pages 1403-1410
Technical Paper | dx.doi.org/10.1080/00295639.2019.1642675
Articles are hosted by Taylor and Francis Online.
Safety analyses of pressurized water reactors and boiling water reactors in the event of small-break loss-of-coolant accidents strongly depend on leakage rate predictions using two-phase critical flow models. The paper aims to revise the critical flow criterion and consider the nonequilibrium phenomena of critical flows in constructing a modified two-phase critical flow model. The model predictions exhibit strong similarities with the experimental values, with prediction deviations of 14.4% for mass fluxes and 19.3% for outlet pressure. The compiled code, according to the proposed model, can be exploited in pressure pipeline designs, providing the theoretical basis for leak-before-break analyses.