Published May 1981
| Version v1
Report
Restricted
Workshop proceedings: corrosion of Inconel 600 steam generator tubing in the tubsheet crevice
Description
The proceedings of a workshop on the problem of the cracking and intergranular attack of Inconel 600 tubing in tubesheet crevices in nuclear reactor steam generators is presented. The objectives of the workshop were to: (1) focus on the problem; (2) identify and prioritize possible mechanisms; (3) focus on the testing necessary to analyze and describe the problem; (4) determine what remedial actions should be taken in the plants; (5) determine what else can be observed from plant data; and (6) provide some assurance that we will be trying to treat the problem and not a symptom of the problem. A summary of the meeting is presented along with each participant's presented material
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A16/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 362 p.
- Report number
- EPRI-WS--80-157
Conference
- Title
- Workshop on corrosion of inconel 600 steam generator tubing in the tubesheet crevice.
- Dates
- 9 - 10 Sep 1980.
- Place
- Palo Alto, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12638971
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; INCONEL 600; MEETINGS; PWR TYPE REACTORS; STEAM GENERATORS; STRESS CORROSION; SURFACE CLEANING; TUBES
- Descriptors DEC
- ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CLEANING; CORROSION; INCONEL ALLOYS; IRON ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; REACTORS; SURFACE FINISHING; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8009163--.