BWR pipe crack remedies evaluation
- 1. Argonne National Lab., IL
Description
This paper presents results on (a) the influence of simulated BWR environments on the stress-corrosion-cracking (SCC) susceptibility of Types 304, 316NG< and 347 stainless steel (SS), (b) fracture-mechanics crack growth rate measurements on these materials and weld overlay specimens in different environments, and (c) residual stress measurements and metallographic evaluations of conventional pipe weldments treated by a mechanical-stress-improvement process (MSIP) as well as those produced by a narrow-gap welding procedure. Crack initiation studies on Types 304 and 316NG SS under crevice and non-crevice conditions in 2890C water containing 0.25 ppm dissolved oxygen with low sulfate concentrations indicate that SCC initiates at very low strains (<3%) in the nuclear grade material. Crack growth measurements on fracture-mechanics-type specimens, under low-frequency cyclic loading, show that the Type 316NG steel cracks at a somewhat lower rate (∼40%) than sensitized Type 304 SS in an impurity environment with 0.25 ppm dissolved oxygen; however, the latter material stops cracking when sulfate is removed from the water. Crack growth in both materials ceases under simulated hydrogen-water chemistry conditions (<5 ppb oxygen) even with 100 ppb sulfate present in the water. An unexpected result was obtained in the test on a weld overlay specimen in the impurity environment, viz., the crack grew to the overlay interface at a nominal rate, branched at 900 in both directions, and then grew at a high rate (parallel to the nominal applied load). Residual stress measurements on MSIP-treated weldments and those produced by a narrow-gap welding procedure indicate that these techniques produce compressive stresses over most of the inner surface near the weld and heat-affected zones
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting. Volume 2. Research in nondestructive evaluation, environmental effects in primary system components, pressure vessel research, irradiation effects on RPV steels, degraded piping research
- Journal Page Range
- p. 101-118.
- Report number
- NUREG/CP--0082-Vol.2
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002088
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; CRACKS; FRACTURE MECHANICS; HEAT AFFECTED ZONE; IMPURITIES; INTERGRANULAR CORROSION; IRRADIATION; PIPES; REACTOR SAFETY; REPAIR; RESEARCH PROGRAMS; RESIDUAL STRESSES; STEEL-CR17NI12MO3; STEEL-CR18NI11NB; STEEL-CR19NI10; STRESS CORROSION; 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; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NIOBIUM ADDITIONS; POWER REACTORS; REACTORS; SAFETY; STAINLESS STEELS; STEELS; STRESSES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT