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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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.”
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.