Published February 1988 | Version v1
Report

BWR pipe crack remedies evaluation

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).