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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.
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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Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Hyoung Tae Kim, Hee Cheon No
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 169-185
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3236
Articles are hosted by Taylor and Francis Online.
An integral response scaling method for reduced-height test facilities is described and validated for the local and the integral phenomena using the RELAP5 thermal-hydraulic code. In the present schematic scaling methodology, the scaling laws are generated from four scaling analyses: three-dimensional differential equation-based scaling analysis, one-dimensional differential equation-based scaling analysis, component-based scaling analysis, and overall integral scaling analysis. Through use of integral response function, scaling parameters related to four types of requirements are identified: time scaling, initial-condition scaling, transient scaling, and bifurcation-phenomena scaling requirements. In the present scaling method, flow velocities in the vertical channel and at break locations of the scaled-down model can be preserved setting up the scaling as R = lR. The significance of the velocity preservation in the reduced-height facility is demonstrated by the RELAP5 code.To validate the present scaling method, similarity criteria from the integral response scaling method are applied to the scaled-down model of the Korea Standard Nuclear Power Plant simulating core boil-off process during midloop operation. The scaled-down model is basically developed with the length and area scales of 1/5 and 1/100, respectively. The integral simulation and local calculations for pot-boiling, blowdown, heat transfer in the steam generator, and off-take are conducted for a loss of RHR during the midloop operation to show the preservation of the similarity criteria using RELAP5.It turns out that the scaled-down model based on the present scaling method maintains well the similarity of the nondimensional parameters for the local phenomena. Furthermore, the integral simulation indicates that there are no noteworthy differences in the general trends between the prototype and scaled models.