Crevice chemistry control in PWR steam generators
- NWT Corp., San Jose, CA (United States)
- Electric Power Research Inst., Palo Alto, CA (United States)
- Commonwealth Edison, Downers Grove, IL (United States)
- Pacific Gas and Electric, Avila Beach, CA (United States)
To establish a basis for predicting and eventually controlling crevice solution chemistry in PWR steam generators, hideout tests were performed at several units. Results indicated that impurity hideout rates varied with the species and with bulk water concentration. Field evaluations of crevice impurity inventory models based on the hideout rate data indicated that further model refinements were necessary, e.g., more frequent quantification of the relation of hideout rates and bulk water concentration. An alternate crevice inventory model based on a real-time mass balance approach also began to be pursued. Modeling results currently are being used at several PWRs to establish a chloride injection rate consistent with development of a near neutral crevice solution to minimize IGA/SCC. Hideout return data are being used to independently establish predictions of crevice chemistry and to substantiate the hideout rate and mass balance model predictions.
- OSTI ID:
- 203744
- Report Number(s):
- CONF-950816-; ISBN 1-877914-95-9; TRN: 96:009710
- Resource Relation:
- Conference: 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995; Other Information: PBD: 1995; Related Information: Is Part Of Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2; Airey, G.; Andresen, P.; Brown, J. [eds.] [and others]; PB: 620 p.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PWR TYPE REACTORS
STEAM GENERATORS
WATER CHEMISTRY
CONTROL
IMPURITIES
MATHEMATICAL MODELS
ADDITIVES
INTERGRANULAR CORROSION
STRESS CORROSION
CRACK PROPAGATION
FORECASTING
MITIGATION
CORROSION PRODUCTS
PH VALUE
SECONDARY COOLANT CIRCUITS
BRAIDWOOD-1 REACTOR
DIABLO CANYON-1 REACTOR
SENSITIVITY ANALYSIS