Tube-to-tubesheet joint test. Volume 2. Final report
Description
The PWR steam generator tube to tubesheet crevice test program was formulated to develop flushing procedures for removing concentrated chemical solutions from partially rolled (deep) tubesheet crevices and to investigate the characteristics of various tube to tubesheet joint crevice configurations with regard to the initiation of concentration processes. The crevice flushing testing indicated that significant fractions of a concentrated sodium hydroxide solution could be transported out of a full depth, unpacked tubesheet crevice by heating and then depressurizing the contents of the crevice. Based upon testing of both packed and unpacked crevices, the most effective flushing procedure was found to utilize the primary coolant system as the heat source, an initial crevice temperature of about 3000F, a nitrogen overpressure in the steam generator, and alternating rapid and slow depressurizations
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A14/MF A01; 1 as DE83902312.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 306 p.
- Report number
- EPRI-NP--3013-Vol.2
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14788294
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CHEMICAL REACTIONS; DEPOSITS; EXPERIMENTAL DATA; HYDRAULICS; PERFORMANCE TESTING; PWR TYPE REACTORS; SODIUM HYDROXIDES; STEAM GENERATORS; SURFACE CLEANING; TUBES; WATER CHEMISTRY
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BOILERS; CLEANING; DATA; HYDROGEN COMPOUNDS; HYDROXIDES; INFORMATION; NUMERICAL DATA; OXYGEN COMPOUNDS; REACTORS; SODIUM COMPOUNDS; SURFACE FINISHING; TESTING; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT