Published 1995
| Version v1
Book
Development of ECP models for BWR applications
Creators
- 1. GE Corporate Research and Development Center, Schenectady, NY (United States)
- 2. GE Vallecitos Nuclear Center, Pleasanton, CA (United States)
- 3. Electric Power Research Inst., Palo Alto, CA (United States)
Description
The electrochemical corrosion potential (ECP) of stainless steel has been measured under simulated Boiling Water Reactor (BWR) coolant circuit conditions using a rotating cylinder electrode. Based on the results of measurements an empirical model has been developed to predict the ECP of structure materials in a BVTR primary circuit as a function of H2, O2, and H2O2 concentrations in reactor coolant and water flow velocity. The ECP modeling results using the H2, O2, and H2O2 concentrations calculated by the radiolysis model are compared with the available reactor internal ECP data obtained in an operating reactor
Additional details
Publishing Information
- Publisher
- NACE International.
- Imprint Place
- Houston, TX (United States)
- ISBN
- 1-877914-95-9
- Imprint Title
- Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2
- Imprint Pagination
- 620 p.
- Journal Page Range
- p. 699-710.
Conference
- Title
- water reactors.
- Acronym
- 7. NACE international symposium on environmental degradation of materials in nuclear power plants
- Dates
- 6-10 Aug 1995.
- Place
- Breckenridge, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27043582
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CHEMICAL REACTION YIELD; CONTROL; CRACK PROPAGATION; ELECTROCHEMISTRY; EXPERIMENTAL DATA; HYDROGEN; INTERGRANULAR CORROSION; MATHEMATICAL MODELS; MITIGATION; OXYGEN; PRIMARY COOLANT CIRCUITS; REACTOR MATERIALS; STAINLESS STEEL-316; STRESS CORROSION; THEORETICAL DATA; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DATA; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NONMETALS; NUMERICAL DATA; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YIELDS
Optional Information
- Secondary number(s)
- CONF-950816--.