Effects of H/sub 2/ Additions on Stress Corrosion Cracking in a Boiling Water Reactor
Journal Article
·
· Corrosion (Houston); (United States)
Controlled amounts of hydrogen were injected into the Dresden-2 boiling water reactor (BWR) during a five week period. The effect of the hydrogen modified water chemistry on major structural alloys used in the BWR system was studied. The studies were conducted in a test facility consisting of two 1 L vessels which were piped to receive reactor water from the discharge side of the main recirculation pump. One of the vessels was used to measure electrochemical potentials. The second vessel was used to perform slow strain rate stress corrosion cracking tests. Electrochemical measurements were conducted continuously during normal BWR operation and during periods of hydrogen injection. The hydrogen injection caused the quantity of dissolved oxygen to decrease, which resulted in a substantial drop in corrosion potentials. At the highest injection rate, the corrosion potential of AISI 304 stainless steel dropped below the potential at which intergranular stress corrosion cracking (IGSCC) could be expected. Stress corrosion tests were conducted on severely sensitized AISI 304 stainless steel and pressure vessel steel. During normal operation, the stainless steel failed primarily by IGSCC. During H/sub 2/ injection when the water contained <20 ppm O/sub 2/, both IGSCC of the stainless steel and transgranular SCC of pressure vessel steel were eliminated.
- OSTI ID:
- 5053919
- Journal Information:
- Corrosion (Houston); (United States), Journal Name: Corrosion (Houston); (United States) Vol. 41:1; ISSN CORRA
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
CORROSIVE EFFECTS
CRACK PROPAGATION
CRYSTAL STRUCTURE
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DRESDEN-2 REACTOR
ELECTROCHEMISTRY
ELEMENTS
ENRICHED URANIUM REACTORS
FLUID-STRUCTURE INTERACTIONS
FRACTURE PROPERTIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDROGEN
HYDROGEN COMPOUNDS
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MICROSTRUCTURE
NICKEL ALLOYS
NONMETALS
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURE VESSELS
REACTOR VESSELS
REACTORS
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
STRESS ANALYSIS
STRESS CORROSION
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THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
CORROSIVE EFFECTS
CRACK PROPAGATION
CRYSTAL STRUCTURE
DESTRUCTIVE TESTING
DRESDEN-2 REACTOR
ELECTROCHEMISTRY
ELEMENTS
ENRICHED URANIUM REACTORS
FLUID-STRUCTURE INTERACTIONS
FRACTURE PROPERTIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDROGEN
HYDROGEN COMPOUNDS
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MICROSTRUCTURE
NICKEL ALLOYS
NONMETALS
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURE VESSELS
REACTOR VESSELS
REACTORS
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
STRESS ANALYSIS
STRESS CORROSION
TESTING
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS