A model for predicting corrosion damage within crevice under heat transfer condition
Description
This paper presents a model based on chemical thermo-hydraulics to quantitatively predict the corrosion damage within crevices under heat transfer conditions. The model considers damage within crevices under heat transfer conditions as a function of corrosion temperature and concentration of chemicals can be extrapolated using data obtained from autoclave tests under the same material and environmental conditions. The model can be used to determine the corrosion temperature and concentration of aggressive chemicals through calculating the localized chemical thermo-hydraulic conditions in crevices to predict corrosion damage. The effect of porous deposits packed within crevices is considered in the model. This paper studied several different geometrical crevices and Zircaloy cladding failure at spacer grids. A test with Zircaloy cladding in simplified spacer grids in a LiOH solution under subcooled boiling condition is described. The predicted results are found to be in good agreement with the experimental data
Additional details
Publishing Information
- Publisher
- The Metallurgical Society Inc.
- Imprint Place
- Warrendale, PA (USA)
- Imprint Title
- Proceedings of the third international symposium on environmental degradation of materials in nuclear power systems
- Journal Page Range
- p. 229-236.
Conference
- Title
- water reactors.
- Acronym
- 3. international symposium on environmental degradation of materials in nuclear power systems
- Dates
- 30 Aug - 3 Sep 1987.
- Place
- Traverse City, MI (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20055539
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CHEMICAL REACTION KINETICS; CORROSION; CORROSION DENTING; EXPERIMENTAL DATA; HEAT TRANSFER; LITHIUM HYDROXIDES; MATERIALS TESTING; THERMODYNAMICS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ALLOYS; CHEMICAL REACTIONS; DATA; DEFORMATION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; HYDROXIDES; INFORMATION; KINETICS; LITHIUM COMPOUNDS; NUMERICAL DATA; OXYGEN COMPOUNDS; POWER REACTORS; REACTION KINETICS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS