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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Kevin Segard, Richard Brock, Keith Higar (U.S. Fuels, Framatome), Sebastian Kuch (Fuels Germany, Framatome)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1234-1247
Framatome has recently developed ARITA, a statistical Non-LOCA methodology based on the external coupling of the 3D core simulator ARTEMIS and the system thermal-hydraulics code S-RELAP5. As part of the qualification of the coupled approach used in ARITA, operating plant transients were analyzed. This paper considers one of these transients; a planned Loss of External Load transient performed on a 1300 MWe plant. This transient was initiated at End-of-Cycle conditions while in coastdown. The purpose of the transient was to measure plant responses to a Loss of External Load. An ARTEMIS/S-RELAP5 model was developed to simulate the transient and provide comparison data. Deviations between calculated and measured results are well behaved and show that ARTEMIS/S-RELAP5 provide a good representation of an operating reactor during transient conditions. The observed maximum deviation in the short-term corrected power is less than 1% rated thermal power, the maximum average coolant temperature deviation is less than 1 °C, and primary pressure difference during the initial peak is within 1 bar, while the peak near the end of the transient is within 2 bar. When steam generator level stabilizes, the final measured level is slightly over-predicted by about 3%. ARTEMIS trends well with the fixed incore detectors.
ARITA, ARTEMIS, COBRA-FLX and S-RELAP5 are trademarks or registered trademarks of Framatome in the USA or other countries.