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Division Spotlight
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.
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.”
Yassin A. Hassan, Andrey A. Troshko
Nuclear Technology | Volume 119 | Number 1 | July 1997 | Pages 29-37
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT77-A35392
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic CATHARE V1.3U code has been used to simulate an International Standard Problem (ISP38) experiment conducted at BETHSY Integral Test Facility located in Grenoble, France. This experiment presents simulation of the loss of residual heat removal system during midloop operation. It involved opening of the pressurizer man way and steam generator outlet plenum man way simultaneously with switching on the heating rod power to simulate the decay heat. The total power level of 138 kW was kept unchanged throughout the test. Mass discharge through both manways led to core boiling and uncovery. The test was stopped when the primary cooling system was filled back to a midloop level. Overall, the code’s prediction and experimental data were found to be in reasonable qualitative agreement. However, the code underestimated the time of the core uncovery and the actuation of the gravity feed injection because of the overprediction of the discharge through the steam generator man way during the initial stage of the transient. This was caused by misestimation of the phase separation effect at the hot leg/surge line tee junction and significant water entrainment into the surge line at the beginning of the test. It was found that the upward tee junction model needs to be refined for the low-pressure transients.