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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
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.