Application of the ATHOS3 code for steam generator thermal hydraulics and fouling analysis
- Electric Power Research Inst., Palo Alto, CA (United States). Nuclear Power Group
- CFD Research Corp., Huntsville, AL (United States)
The steam generator is a most important component in the coolant loop of Pressurized Water Reactors. Although designed for a 30--40 year operating life, severe material degradation problems have occurred within the first ten years of operation. Performance and reliability evaluations are required on a continuing basis to develop solutions and design modifications to ensure reliable operation of these systems. Thermal hydraulic analysis provides basic information such as velocity and void fraction distributions within the secondary side of the steam generator needed for the evaluation of sludge deposition, bundle fouling, tube vibration, fretting, wear and fatigue. This paper presents detailed thermal hydraulic analysis of several steam generator designs, and analyzes the correlation between thermal hydraulic distributions, sludge deposition and bundle fouling using a recent model for sludge transport and deposition. The correlation between thermal hydraulic distributions and other degradation mechanisms such as circumferential cracking of tubes is also presented. The results show that there is a strong correlation between flow velocity, void fraction and sludge deposition. The calculated sludge deposit potential maps are in very good agreement with the observed results within operating steam generators.
- OSTI ID:
- 277836
- Report Number(s):
- CONF-960306-; ISBN 0-7918-1226-X; TRN: 96:018245
- Resource Relation:
- Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of ICONE-4: Proceedings. Volume 5: Radioactive waste disposal; Decontamination and decommissioning; Aging assessment and license renewals; Global advances in nuclear codes and standards; Major component reliability; Rao, A.S. [ed.] [General Electric Nuclear Energy, San Jose, CA (United States)]; Duffey, R.B. [ed.] [Brookhaven National Lab., Upton, NY (United States)]; Elias, D. [ed.] [Commonwealth Edison, Downers Grove, IL (United States)]; PB: 525 p.
- Country of Publication:
- United States
- Language:
- English
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