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U.S. Department of Energy
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Thermal-hydraulic code qualification: ATHOS2 and data from Bugey 4 and Tricastin 1. Final report. [PWR]

Technical Report ·
OSTI ID:6344207
Measured data from steam generators at the Bugey 4 and Tricastin 1 nuclear power plants operated by Electricite de France (EdF) have been used in the qualification of the ATHOS2 computer code. ATHOS2 is a three-dimensional, two-phase thermal-hydraulic code for the steady-state and transient analysis of recirculating-type steam generators. Predicted data for circulation ratio and secondary fluid temperature just above the tube sheet have been compared with corresponding data measured by EdF during on-site testing of Westinghouse Model 51A (Bugey 4) and 51M (Tricastin 1) steam generators. Comparative analyses have been performed for steady-state operating conditions at five power levels for each plant installation. The transient capabilities of the ATHOS2 code were examined in the simulation of an open-grid (load reject from 100% power) test conducted at Bugey 4. Results show that predicted data for secondary fluid temperature at eight locations just above the tube sheet are typically within 1.5/sup 0/C of measured data.
Research Organization:
JAYCOR, San Diego, CA (USA)
OSTI ID:
6344207
Report Number(s):
EPRI-NP-2872; ON: DE83901875
Country of Publication:
United States
Language:
English