Effects of LOMI (low oxidation state metal ion) decontamination and preoxidation processes on stainless steel-clad low-alloy steel
Technical Report
·
OSTI ID:7014382
- General Electric Co., San Jose, CA (USA). Nuclear Energy Div.
Standard 1T WOL (wedge opening load) bolt-loaded specimens were fabricated from a heat of SA302 Gr B low alloy steel and clad with 308L stainless steel. This quenched and tempered SA302 Gr B steel possesses a bainitic microstructure and is one of the key steels for boiling water reactor (BWR) pressure vessel fabrication. Fatigue precracks were produced which passed through the 308L clad layer into low alloy steel. This through-clad precracking, together with the galvanic coupling of austenitic and ferritic steels, is considered to be the worst condition for the stress corrosion cracking of the reactor pressure vessel (RPV) wall. The precracked specimens were loaded to an applied stress intensity of approximately 45 ksi (in.){sup 1/2}. Scanning electron microscopy (SEM) and optical metallographic examinations revealed both intergranular (IGSCC) and transgranular (TGSCC) branched stress corrosion cracks beyond the tip of fatigue precracks in the Peach Bottom 3 in-plant LOMI/NP/LOMI exposed specimens. The low temperature BWR water autoclave immersion test was performed to simulate the time/temperature cycle of the Peach Bottom 3 in-plant decontamination process but without addition of any decontamination solvents. Results of this study also indicated that the NP/LOMI process tended to promote stress corrosion crack propagation in the pressure vessel low alloy steel. Although the degree of susceptibility and crack morphology may depend on process time, temperature, and solvent concentration, it appears that nitric acid is the key ingredient for the promotion of both IGSCC and TGSCC.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA); General Electric Co., San Jose, CA (USA). Nuclear Energy Div.
- Sponsoring Organization:
- EPRI
- OSTI ID:
- 7014382
- Report Number(s):
- EPRI-NP-6730
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360102 -- Metals & Alloys-- Structure & Phase Studies
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CLEANING
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
DECONTAMINATION
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LOW CA
MATERIALS
NICKEL ALLOYS
PEACH BOTTOM-3 REACTOR
POWER REACTORS
PRESSURE VESSELS
PROGRESS REPORT
REACTOR MATERIALS
REACTORS
STAINLESS STEEL-308L
STAINLESS STEELS
STEEL-CR20NI11-L
STEELS
STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360102 -- Metals & Alloys-- Structure & Phase Studies
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CLEANING
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
DECONTAMINATION
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LOW CA
MATERIALS
NICKEL ALLOYS
PEACH BOTTOM-3 REACTOR
POWER REACTORS
PRESSURE VESSELS
PROGRESS REPORT
REACTOR MATERIALS
REACTORS
STAINLESS STEEL-308L
STAINLESS STEELS
STEEL-CR20NI11-L
STEELS
STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS