Investigation of corrosion and stress corrosion cracking in bolting materials on light water reactors
Description
Laboratory experiments performed at Brookhaven National Laboratory have shown that the concentration of boric acid to a moist paste at approximately the boiling point of water can produce corrosion rates of the order of approximately 3.5mm per year on bolting and piping materials, which values are consistent with service experience. Other failure evaluation experience has shown that primary coolant-lubricant interaction may lead to stress corrosion cracking (SCC) of steam generator manway studs. An investigation was also performed on eleven lubricants and their effects on A193 B7 and A540 B24 bolting materials. H2S generation by the lubricants, coefficient of friction results and transgranular SCC of the bolting materials in steam are discussed. (author)
Additional details
Publishing Information
- Journal Title
- Int. J. Press. Vessels Piping
- Journal Volume
- 26
- Journal Issue
- 2
- Series
- Int. J. Press. Vessels Piping.
- Journal Page Range
- 87-96
- ISSN
- 0308-0161
- CODEN
- PRVPA
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 18065901
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BORIC ACID; CRACKS; FASTENERS; LUBRICANTS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STEAM GENERATORS; STRESS CORROSION
- Descriptors DEC
- BOILERS; BORON COMPOUNDS; CHEMICAL REACTIONS; COOLING SYSTEMS; CORROSION; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS