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Division Spotlight
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Lainsu Kao, Ping-Hue Huang
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 382-388
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT99-A3008
Articles are hosted by Taylor and Francis Online.
The reactor coolant pump locked rotor analysis methodology developed by Taiwan Power Company for application to pressurized water reactors (PWRs) is presented. The proposed locked rotor analysis methodology utilizes two computer codes developed or sponsored by Electric Power Research Institute (EPRI): system transient analysis code RETRAN-02 and fuel rod evaluation code FREY. RETRAN-02 determines the transient system responses and the peak reactor coolant system (RCS) pressure. FREY utilizes the core power and core flow transients generated by RETRAN-02 to evaluate the peak clad temperature (PCT) during the transient. FREY is needed for PCT calculations since the conservative modeling assumptions with respect to the PCT can be different from those with respect to the peak RCS pressure. Both computer codes have been properly qualified by benchmarking against the vendor's results.An asymmetric-flow condition would be developed following the initiation of the locked rotor incident. Although there is no guidance in EPRI's "Reactor Analysis Support Package, Volume 3: PWR Event Analysis Guidelines" for the modeling of incomplete mixing at the downcomer and the lower plenum, it was observed from the sensitivity results that the maximum RCS pressure is very sensitive to the amount of mixing. Thus, a split-core model is required to adequately simulate the asymmetric-flow effect.
