Corrosion in nuclear power plants and it implication in the leak before break criteria
Description
The corrosion in a general way can be defined like a chemical or electrochemical reaction, which is carried out in the surface of the metallic materials exposed to a specific medium. Due to the operation conditions in the nuclear power plants are practically fixed and its modification in most of the cases is difficult or expensive, the natural tendency to prevent the corrosion has been generally directed toward the selection of materials. Numerous materials have been employees as substitute of the traditional steels, among other the stabilized stainless steels, those of extra low carbon and numerous nickel base alloys. The basic evaluation that establishes the approach Leak before break (LBB) it involves the analysis by means of 'fracture mechanics' of a postulated crevice that it crosses the thickness of the material, which causes a same flight, with a margin of safety, to the detection limit that it has for a shutdown of the reactor. Due to the crevice size postulated, it cannot be established highly starting from the mechanical properties of the material since these its will be affected by the corrosion mechanisms that can settle down, it was determined that the implementation of the LBB criteria, it cannot be established for components or systems that its are susceptible of suffering corrosion. (Author)
Availability note (English)
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37070749.pdf
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Additional details
Additional titles
- Original title (Spanish)
- Corrosion en centrales nucleares y su implicacion en el criterio de fuga antes de ruptura
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- IA--92-202
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 37070749
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CORROSION; CREVICE CORROSION; DIAGRAMS; FAILURES; INCONEL 600; INCONEL 82; INTERGRANULAR CORROSION; LEAKS; NUCLEAR POWER PLANTS; REACTOR COOLING SYSTEMS; SHROUDS; STAINLESS STEEL-304; STRESS CORROSION; TIME DEPENDENCE
- Descriptors DEC
- ALLOY-NI73CR20MN3NB3; ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INCONEL ALLOYS; INFORMATION; IRON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; MANGANESE ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NIOBIUM ALLOYS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; THERMAL POWER PLANTS; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- INIS-MX-RI--0063