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The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
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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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Kentucky legislature sends nuclear bills to governor
Kentucky’s Republican-majority legislature passed a bill this past week that could bring nuclear energy to the “coal-is-king” state as lawmakers broadly seek solutions to reduce carbon emissions. The bill went to Democratic Gov. Andrew Beshear on Monday for final approval.
Tae-Joon Kim, Valeriy S. Yugay, Ji-Young Jeong, Jong-Man Kim, Byeung-Ho Kim, Tae-Ho Lee, Yong-Bum Lee, Yeong-Il Kim, Dohee Hahn
Nuclear Technology | Volume 170 | Number 2 | May 2010 | Pages 360-369
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT10-A9489
Articles are hosted by Taylor and Francis Online.
This technical note presents the results of an experimental study of the role of water in sodium leak noise spectrum formation and at various water/steam leak rates of <1.0 g/s. The conditions and ranges for the existence of bubbling and jetting modes in water/steam outflow into circulating sodium through an injector device were determined to simulate a defect in the wall of the heat-transmitting tube of a sodium-water steam generator (SG). Based on experimental leak noise data, the simple dependency of the acoustic signal level on the leak rate of a microleak and small leaks at different frequency bands was presented for the principal analysis to develop an acoustic leak detection methodology for a KALIMER-600, 600-MW(thermal) reactor (K-600) SG, with the operational experiences for noise analysis and measurements of the Bystry neutron (fast neutron) reactor BN-600. Finally, the methodology was tested with the Korea Atomic Energy Research Institute (KAERI) acoustic leak detection system using sodium-water reaction signals of the Institute of Physics and Power Engineering and background noise of the Prototype Fast Reactor (PFR) superheater for methodology development of KAERI, and it was able to detect a leak rate of under 1 g/s and a signal-to-background noise ratio of -22 dB, using this system and methodology.