BWR pipe crack remedies evaluation
Creators
- 1. Argonne National Lab., IL (USA)
Description
Piping in light-water-reactor power systems has been affected by several types of environmental degradation. This paper presents results from studies of (1) stress corrosion crack growth in fracture mechanics specimens of modified Type 347 SS and Type 304/308L SS weld overlay material, (2) heat-to-heat variations in stress corrosion cracking (SCC) of Types 316NG and 347 SS, (3) SCC of sensitized Type 304 SS in water with cupric ion or organic acid impurities, (4) electrochemical potential (ECP) measurements under gamma irradiation, (5) SCC of ferritic steels, (6) strain-controlled fatigue of Type 316NG SS in air at ambient temperature, and (7) through-wall residual stress measurements and finite-element calculations of residual stresses in weldments treated by a mechanical stress improvement process (MSIP). Fracture-mechanics crack-growth-rate tests on Type 316NG SS have shown that transgranular cracking can occur even in high purity environments, whereas no crack growth was observed in Type 347 SS even in impurity environments. In tests on weld overlay specimens, the cracks branched when they approached the overlay, and then grew parallel to interface. Type 304 SS, cupric ions at concentrations greater than ∼ 1 ppm were found to be deleterious, whereas organic acids were not detrimental. Tests on ferritic steels indicate a strong correlation between the sulfur content of the steels and susceptibility to SCC. External gamma radiation fields produced a large positive shift in the ECP of Type 304 SS at low dissolved-oxygen concentrations (< 5 ppb). Fatigue data for Type 316NG SS are consistent with the ASME code mean curve at high strains, but fall below the curve at low strains. Calculations of the residual stresses produced by MSIP are in reasonable agreement with experimental measurements. 37 references
Additional details
Publishing Information
- Imprint Title
- Proceeding of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 2
- Journal Page Range
- p. 381-405.
- Report number
- NUREG/CP--0091-Vol.2
Conference
- Title
- 15. water reactor safety information meeting.
- Dates
- 26-30 Oct 1987.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20018093
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COPPER; CRACK PROPAGATION; ELECTRIC CONDUCTIVITY; ELECTROCHEMICAL CORROSION; FATIGUE; FERRITIC STEELS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; GAMMA RADIATION; HEAT TREATMENTS; ORGANIC ACIDS; PIPES; RADIATION EFFECTS; STEEL-CR17NI12MO3; STEEL-CR18NI11NB; STEEL-CR19NI10; STEEL-CR20NI11; STRESS CORROSION; STRESSES; TEMPERATURE DEPENDENCE; WATER CHEMISTRY; WELDED JOINTS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STE; CORROSION; CORROSION RESISTANT ALLOYS; ELECTRICAL PROPERTIES; ELECTROMAGNETIC RADIATION; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IONIZING RADIATIONS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICAL PROPERTIES; MECHANICS; METALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NIOBIUM ADDITIONS; NUMERICAL SOLUTION; ORGANIC COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; RADIATIONS; REACTORS; STAINLESS STEELS; STEELS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT