Published June 1987
| Version v1
Report
PWR electrochemical potential measurements
Description
This presentation provides a status report on the preparations for the installation of an electrochemical potential test facility in the primary loop of the Trojan Nuclear Power Station. The project involved the design, fabrication, and installation of the test facility, and the qualification of reference electrodes to be used in the facility
Additional details
Publishing Information
- Imprint Title
- Proceedings: 1985 workshop on primary-side stress corrosion cracking of PWR steam generator tubing
- Journal Page Range
- p. 30.1-30.18.
- Report number
- EPRI-NP--5158
Conference
- Title
- Workshop on primary-side stress corrosion cracking of PWR steam generator tubing.
- Dates
- 20-22 Mar 1985.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19046283
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- DIAGRAMS; ELECTROCHEMICAL CORROSION; ELECTROCHEMISTRY; ELECTRODES; EXPERIMENTAL DATA; HYDROGEN; POTENTIALS; PRIMARY COOLANT CIRCUITS; STEEL-CR17NI12MO3; TESTING; TROJAN REACTOR; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STE; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DATA; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NONMETALS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT