Steam generator performance degradation
- Energy Management Services, Little Rock, AR (United States)
A survey was conducted to determine the range and severity of steam generator performance degradation effects experienced by PWRs in the United States. The survey results were tabulated and correlated with steam generator age and design. Operating experience at several PWRs was examined in detail. The operating experience at US PWRs was compared to that of PWRs in Japan and Germany. Possible causes for the performance degradation were postulated and evaluated. The sensitivity of steam generator output pressure to changes in various parameters (such as fouling factor, average reactor coolant temperature, and percentage of steam generator tubes plugged) was calculated. These calculations were used in the evaluation of possible causes of steam generator performance degradation. Several deposit exfoliation scenarios were evaluated in terms of the calculated effect on fouling factor trends and associated steam generator output pressure trends. 15 refs., 32 figs., 7 tabs.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (United States); Energy Management Services, Little Rock, AR (United States)
- Sponsoring Organization:
- EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
- OSTI ID:
- 5176549
- Report Number(s):
- EPRI-NP-7524
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
STEAM GENERATORS
FOULING
RELIABILITY
COMPARATIVE EVALUATIONS
HEAT TRANSFER
HYDRAULICS
MONITORING
NUCLEAR POWER PLANTS
OPERATION
PERFORMANCE
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SURVEYS
TUBES
BOILERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EVALUATION
FLUID MECHANICS
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled