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Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0048814
EISBN: 978-1-62708-229-7
... Abstract A nuclear steam-generator vessel constructed of 100-mm thick SA302, grade B, steel was found to have a small leak. The leak originated in the circumferential closure weld joining the transition cone to the upper shell. The welds had been fabricated from the outside by the submerged arc...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0090881
EISBN: 978-1-62708-229-7
... Abstract A power plant using two steam generators (vertical U-tube and shell heat exchangers, approximately 21 m (68 ft) high with a steam drum diameter of 6 m (20 ft)) experienced a steam generator tube rupture. Each steam generator contained 11,012 Inconel alloy 600 (nickel-base alloy) tubes...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0090277
EISBN: 978-1-62708-229-7
... Abstract A rupture of a thirty-year-old U-tube on a steam generator for a closed-cycle pressurized-water nuclear power plant occurred, resulting in limited release of reactor water. A typical tube bundle can be over 9 m (30 ft) tall and 3 m (10 ft) in diam with over 3,000 22-mm (7/8-in.) diam...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.modes.c9001240
EISBN: 978-1-62708-234-1
... Abstract A heat exchanger made of a pipe in which oil was heated from the outside from approximately 90 deg C to 170 deg C, by superheated steam of about 8 to 10 atmospheres had developed a leak at the rolled joint of the pipe and pipe bottom. The pipes were supposed to be made from St 35.29...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001609
EISBN: 978-1-62708-229-7
... Abstract Alloy 430 stainless steel tube-to-header welds failed in a heat recovery steam generator (HRSG) within one year of commissioning. The HRSG was in a combined cycle, gas-fired, combustion turbine electric power plant. Alloy 430, a 17% Cr ferritic stainless steel, was selected because...
Series: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001051
EISBN: 978-1-62708-214-3
..., the A302 material was also susceptible to transgranular stress-corrosion cracking (SCC) in the PAT environment if copper was present in solution. Specimen Selection Three elliptically shaped boat samples of the shell material were evaluated: Sample A from steam generator No. 2, which was cut...
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Published: 01 January 2002
Fig. 16 Cross section through leak in steam-generator wall. Crack extends across weld metal, base metal, and HAZ. Erosion obliterated much of the original crack detail. More
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Published: 01 January 2002
Fig. 17 Fracture morphology of steam-generator wall in a region where regularly spaced striations typical of fatigue are evident. More
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Published: 01 January 2002
Fig. 18 Fracture surface of a failed steam-generator sample. The fracture morphology is characteristic of fatigue cracking, but 1 ppm of Ce − under constant extension rate testing produced this same fracture morphology in laboratory tests. The initiation site is on the inside surface More
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Published: 01 January 2002
Fig. 10 Photographs of a ruptured Inconel 600 steam generator tube. (a) Tube rupture. (b) SEM fractograph showing the IG fracture surface. (c) Micrograph showing the IG attack that extended from the OD surface More
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Published: 01 January 2002
Fig. 9 Cross-section schematic drawing of a steam generator showing U-tube bundle More
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Published: 01 June 2019
Fig. 1 Heat-recovery steam generator More
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Published: 01 June 2019
Fig. 1 Photographs of a ruptured Inconel 600 steam generator tube. (a) Tube rupture. (b) SEM fractograph showing the IG fracture surface. (c) Micrograph showing the IG attack that extended from the OD surface More
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Published: 01 June 2019
Fig. 1 Cross-section schematic drawing of a steam generator showing U-tube bundle More
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Published: 01 June 2019
Fig. 1 Cross section through leak in steam-generator wall. Crack extends across weld metal, base metal, and HAZ. Erosion obliterated much of the original crack detail. More
Image
Published: 01 June 2019
Fig. 2 Fracture morphology of steam-generator wall in a region where regularly spaced striations typical of fatigue are evident. More
Image
Published: 01 June 2019
Fig. 3 Fracture surface of a failed steam-generator sample. The fracture morphology is characteristic of fatigue cracking, but 1 ppm of Ce − under constant extension rate testing produced this same fracture morphology in laboratory tests. The initiation site is on the inside surface More
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Published: 15 January 2021
Fig. 9 Cross-sectional schematic drawing of a steam generator showing U-tube bundle More
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Published: 30 August 2021
Fig. 65 Cross section through leak in steam-generator wall. Crack extends across weld metal, base metal, and heat-affected zone. Erosion obliterated much of the original crack detail More
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Published: 30 August 2021
Fig. 66 Fracture morphology of steam-generator wall in a region where regularly spaced striations typical of fatigue are evident More