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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Jun 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Sung Jin Lee, Michael Ickes, Jeffrey L. Arndt, Michael Epstein, Asfaq Patel, Paolo Ferroni
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 666-680
Research Article | doi.org/10.1080/00295450.2023.2197667
Articles are hosted by Taylor and Francis Online.
Westinghouse is developing a lead-cooled fast reactor (LFR) as its next-generation utility-scale nuclear power plant. To support its development, Westinghouse and its partners are building 10 test facilities to demonstrate key LFR phenomena, materials, and components in liquid lead. These test infrastructures are distributed across several institutions, and this paper focuses on those located within Westinghouse. It describes three state-of-the-art test rigs being installed in the Westinghouse facility in Springfields, United Kingdom, to test materials in liquid lead and to investigate key LFR phenomena, which will also be used to validate modeling and simulation tools. These facilities address material corrosion/erosion testing (MELECOR), lead freezing and under-lead viewing testing (LEFREEZ), and primary heat exchanger failure testing (LEWIN). This paper also describes the first liquid-lead test system to become operational at Westinghouse at the company’s site in Churchill, Pennsylvania, i.e., a test rig named HELMET to conduct tensile tests in a molten-lead environment to investigate the potential susceptibility of LFR candidate materials to liquid-metal embrittlement.