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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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August 2024
Nuclear Technology
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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.”
Tom Elicson, Hugh Luo, David Luxat (Jensen Hughes), Lajos Tarczal (Paks Nuclear Power Plant), Tom Kindred (EPRI)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 365-378
The MAAP v5.03 computer program was modified to incorporate the unique features of the VVER plant design to provide a state-of the-art severe accident analysis code for the VVER plants. The MAAP5-VVER code is applicable to the VVER-440, VVER-1000, and VVER-1200 plant designs and is capable of accurately modeling scenarios with in-vessel melt retention (IVMR), which is a crucial VVER accident management strategy, and PRISE accidents (large primary-to-secondary leaks) which are key contributors to plant risk. The MAAP5-VVER code version is intended to be applied to accident management analyses as well as Level 1 and Level 2 PRA analyses.
To ensure that the MAAP5-VVER code adequately addresses phenomena and capabilities important to the expected VVER applications, the MAAP5-VVER code is undergoing verification and validation (V&V) testing prior to final code release. The V&V test plan is designed to provide complete coverage of the MAAP5-VVER specific models and important modeling capabilities. Additionally, the validation exercises consist of data for both the VVER-440 and VVER-1000 plants designs obtained from scaled experiments, full scale plant tests, and other detailed code calculations.
This paper provides an overview of the MAAP5-VVER modeling capabilities, discusses the MAAP5-VVER V&V testing program, and presents preliminary results for a benchmark against the IAEA-SPE-3 test performed at the PMK-2 scaled test facility.