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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.”
Michitsugu Mori
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 260-274
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2838
Articles are hosted by Taylor and Francis Online.
The benchmarking and qualification analyses of RETRAN-03 (RETRAN-3D) for boiling water reactor (BWR) stability analyses were carried out by comparison with the frequency-domain stability analysis code NUFREQ-NPT with the stability test data of the Peach Bottom Unit 2. The sensitivities of model parameters were studied in terms of the type of equation model, vapor-liquid interface heat transfer coefficient in upper downcomer, method of characteristics (MOC) model, proportionality constant in the pressure change mass transfer term, and nodalization of a core for the turbine trip test analyses. The sensitivity studies of the model parameters to the decay ratio in stability analyses were performed on the number of core channels, type of equation model, nodalization of a core, perturbation type of disturbance, slip model, proportionality constant in the pressure change mass transfer term, Courant number, MOC model, and kinetics model. The models were selected for the turbine trip tests analyses and for stability tests analyses, based on the sensitivity studies. The model used to analyze stability in RETRAN-03 adopted the five-equations with the MOC, and two-channel models for the core heating region divided into 40 nodes despite 24 nodes used for the turbine trip test analyses. The validation of the model was confirmed by the analyses of the turbine trip tests of the Peach Bottom Unit-2. The stability analyses with the test data and the benchmarking of RETRAN-03 compared with the frequency-domain stability analysis code NUFREQ-NPT in BWR stability exhibit verification and validation within the applicable limitation of the code.