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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
Neutron noise monitoring during plant operation expedites flexure replacement at Salem-1
The nuclear industry has historically relied on intermittent ultrasonic test and visual inspections of pressurized water reactor components to identify and manage degradation. While this reactive approach has proven to be effective, imagine a scenario in which the degradation could propagate throughout the reactor internals, making a more proactive measure necessary to avoid a major enterprise risk to the plant. Could a utility identify the onset of degradation within the reactor internals during plant operation? If so, could a repair be developed prior to the next refueling outage to prevent additional, cascading degradation? That is exactly the situation that Public Service Enterprise Group (PSEG) and Westinghouse engineers were able to navigate over the course of the 2019–2020 operating cycle at Salem Unit 1, resulting in a tremendous success for the plant and a historic landmark in the nuclear industry, while earning the team a 2021 Nuclear Energy Institute Top Innovative Practice (TIP) award.
H. Jin, Y. Wu, J. Qin, F. Liu, F. Long, M. Yu, Q. Han, C. Huang
Fusion Science and Technology | Volume 74 | Number 3 | October 2018 | Pages 211-218
Technical Note | dx.doi.org/10.1080/15361055.2017.1421365
Articles are hosted by Taylor and Francis Online.
Modified stainless steel 316LN is selected as a candidate material for the China Fusion Engineering Test Reactor (CFETR) central solenoid model coil (CSMC) because of the high strength combined with good ductility at cryogenic temperature. The tensile properties, fatigue crack growth rate, and fracture toughness of the SS316LN tube in solution-annealed and aged (575°C/100 h and 650°C/100 h) conditions were evaluated at 4.2 K. The fatigue crack growth and tensile properties for the solution-annealed conduit were high enough to satisfy the design requirements for CFETR CSMC. However, the fracture toughness of the aged conduit is not satisfied, since there was a significant decline from 280 to 110 MPa·m1/2 after cold working and aging treatments. The chemical compositions and fractures have been analyzed to assess the reason and recommend modifications that could improve fracture toughness and fatigue crack growth properties.