ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
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.