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UNS N06600
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Book Chapter
Failure of Nickel-Base Superalloy Heat-Exchanger Tubes in a Black Liquor Heater
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001311
EISBN: 978-1-62708-215-0
... Abstract Several nickel-base superalloy (UNS N06600) welded heat-exchanger tubes used in processing black liquor in a kraft paper mill failed prematurely. Leaking occurred through the tube walls at levels near the bottom tube sheet. The tubes had been installed as replacements for type 304...
Abstract
Several nickel-base superalloy (UNS N06600) welded heat-exchanger tubes used in processing black liquor in a kraft paper mill failed prematurely. Leaking occurred through the tube walls at levels near the bottom tube sheet. The tubes had been installed as replacements for type 304 stainless steel tubes. Visual and stereoscopic examination revealed three types of corrosion on the inside surfaces of the tubes: uniform attack, deeper localized corrosive attack, and accelerated uniform attack. Metallographic analysis indicated that pronounced dissimilar-metal corrosion had occurred in the base metal immediately adjacent to the weld seam. The corrosion was attributed to exposure to nitric acid cleaning solution and was accelerated by galvanic differences between the tubes and a stainless steel tube sheet and between the base metal of the tubes and their dendritic weld seams. A change to type 304 stainless steel tubing made without dendritic weld seams was recommended.
Book Chapter
Failure of an Inconel Clad Carbon Steel Inlet Cone of the Pandia Digester
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.pulp.c9001563
EISBN: 978-1-62708-230-3
.... As a corrective measure, a solid Inconel liner was recommended in the areas of direct steam impingement. Cladding Inlet cones Paper machines Inconel 600 UNS N06600 ASME SA212-B Intergranular corrosion Erosion - corrosion The Inconel clad carbon steel inlet cone failed in a localized area after 7...
Abstract
An Inconel-clad SA-212 Grade B carbon steel inlet cone with an anticipated 25-year service life failed in a localized area after only seven years of service. The failure was caused by an erosion/corrosion leak at the midsection. Erosion/corrosion was confined to a localized area directly facing the steam inlet nozzle. The Inconel cladding was intact elsewhere in the inlet cone with insignificant corrosion-related degradation. In the absence of the conditions that led to erosion/corrosion, the Inconel clad carbon steel was considered adequate for the intended service. As a corrective measure, a solid Inconel liner was recommended in the areas of direct steam impingement.
Book Chapter
Stress-Corrosion Cracking of an Inconel 600 Safe-End on a Reactor Nozzle
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0091655
EISBN: 978-1-62708-229-7
... made. Intergranular corrosion Nozzles Nuclear reactor components Inconel 600 UNS N06600 Stress-corrosion cracking Intergranular fracture Cracking occurred in an ASME SB166 Inconel 600 safe-end forging on a nuclear reactor coolant water recirculation nozzle while it was in service...
Abstract
Cracking occurred in an ASME SB166 Inconel 600 safe-end forging on a nuclear reactor coolant water recirculation nozzle while it was in service. The safe-end was welded to a stainless-steel-clad carbon steel nozzle and a type 316 stainless steel transition metal pipe segment. An Inconel 600 thermal sleeve was welded to the safe-end, and a repair weld had obviously been made on the outside surface of the safe-end to correct a machining error. Initial visual examination of the safe-end disclosed that the cracking extended over approximately 85 deg of the circular circumference of the piece. Investigation (visual inspection, on-site radiographic inspection, limited ultrasonic inspection, chemical analysis, 53x metallographic cross sections and SEM images etched in 8:1 phosphoric acid) supported the conclusion that the cracking mechanism was intergranular SCC. No recommendations were made.
Book Chapter
Intergranular Fracture of Steam Generator Tubes
Available to PurchaseSeries: 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
... power generation Steam generators Tubes Inconel 600 UNS N06600 Intergranular fracture Power plants use steam generators, which have hot reactor coolant water flowing through the generators. One power plant experienced a steam generator tube rupture in the early 1990s. Metallurgical evaluation...
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 measuring 19 mm OD, nominal wall thickness of 1.0 mm (0.042 in.), and average length of 18 m (57.75 ft). The original operating temperature of the reactor coolant was 328 deg C (621 deg F). A tube removal effort was conducted following the tube rupture event. Investigation (visual inspection, SEM fractographs, and micrographs) showed evidence of IGSCC initiating at the OD and IGA under ridgelike deposits that were analyzed and found to be slightly alkaline to very alkaline (caustic) in nature. Crack oxide analysis indicated sulfate levels in excess of expected values. The analysis supported the conclusion that that the deposits formed at locations that experienced steam blanketing or dryout at the higher levels of the steam generators. Recommendations included steam generator water-chemistry controls, chemical cleaning, and reduction of the primary reactor coolant system temperature.
Book Chapter
Failure of a Stirling Engine Heat Pipe
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001032
EISBN: 978-1-62708-214-3
... the heat flux, redesigning the wick, and reducing the oxygen content of the sodium. Engine components Evaporators Fins Solar power generation Space flight Stirling engines 316 UNS S31600 Inconel 600 UNS N06600 Intergranular fracture Intergranular corrosion High-temperature corrosion...
Abstract
A Stirling engine heat pipe failed after only 2h of operation in a test situation. Cracking at the leading edge of an evaporator fin allowed air to enter the system and react with the sodium coolant. The fin was fabricated from 0.8 mm (0.03 in.) thick Inconel 600 sheet. The wick material was type 316 stainless steel. Macro- and microexaminations of specimens from the failed heat pipe were conducted. The fin cracking was caused by overheating that produced intergranular corrosion in both the fin and the wick. Recommendations for alleviating the corrosion problem included reducing the heat flux, redesigning the wick, and reducing the oxygen content of the sodium.
Book Chapter
Combined EDX/AES Analysis of Failed Inconel 600 Steam Line Bellows
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.pulp.c0045911
EISBN: 978-1-62708-230-3
... N06600 Intergranular fracture Within the first few months of operation of a 8-km (5-mile) long 455-mm (18-in.) diam high-pressure steam line between a coal-fired electricity-generating plant and a paper mill, several of the Inconel 600 bellows failed. The steam line operated at 6030 kPa (875 psi...
Abstract
Within the first few months of operation of an 8 km (5 mile) long 455 mm (18 in.) diam high-pressure steam line between a coal-fired electricity-generating plant and a paper mill, several of the Inconel 600 bellows failed. The steam line operated at 6030 kPa (875 psi) and 420 deg C (790 deg F). Metallographic sections, energy-dispersive x-ray spectra, chemical analyses, tensile tests, and Auger microscope analyses showed the failed bellows met the specifications for the material. However, investigation also showed entire oxide thickness was contaminated with relatively large amounts of sodium, calcium, potassium, aluminum, and sulfur, alkali, alkali earth, and other contaminants that completely permeated even the thin oxides on the fracture surfaces. Additional investigation of the purity of the steam itself as reported by the power plant showed that corrosion and cracks were ultimately caused by the steam. While under normal operation, the steam's purity posed no problem to the material, during boiler cleaning operations, the generating plant had allowed contamination to get into the steam line.
Book Chapter
Cracking in a Steam Generator U-Tube
Available to PurchaseSeries: 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
... Residual stresses Steam generators Tube components Tubes Inconel 600 UNS N06600 Intergranular fracture Stress-corrosion cracking A steam generator is a key component used in the generation of steam in a closed-cycle pressurized-water nuclear power plant. It is essentially a large heat exchanger...
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 Inconel Alloy 600 tubes. Tube support plates (TSP) separate the tubes and allow flow of the heating water/steam. Inconel Alloy 600 is susceptible to intergranular stress-corrosion cracking over time, so investigation included review of operational records, maintenance history, and procedures. It also included FEA (thermal gradients, nonlinear material behavior, residual stress, changes in wall thickness during the formation of U-bends, and TSP distortions near the ruptured tube) of three-dimensional solid models of the U-tubes. The conclusion was that distortion of the TSPs and resulting “pinching” of the U-tubes, combined with the operational stresses, caused high stresses at the location where the tube cracked. The stresses were consistent with those required to initiate and propagate a longitudinal crack.
Book Chapter
Failure Analysis of an Exhaust Diffuser Assembly
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001304
EISBN: 978-1-62708-215-0
... defects Welded joints UNS S31000 UNS S40500 UNS N06600 310 COR-TEN 405 Inconel 600 Joining-related failures Fatigue fracture Background An exhaust diffuser assembly that handled air at about 450°C (850°F) failed prematurely in service after approximately 5000 h of operation. The failure...
Abstract
An exhaust diffuser assembly failed prematurely in service. The failure occurred near the intake end of the assembly and involved fracture in the diffuser cone (Corten), diffuser in take flange (type 310 stainless steel), diffuser exit flange (type 405 stainless steel), expansion bellows (Inconel 600), and bellows intake flange (Corten). Individual segments of the failed subassemblies were examined using various methods. The analysis indicated that the weld joint in the diffuser intake flange (type 310 stainless steel to Corten steel) contained diffusion-zone solidification cracks. The joints had been produced using the mechanized gas-metal arc welding process. Cracking was attributed to improper control of welding parameters, and failure was attributed to weld defects.
Book Chapter
Heat Exchanger Corrosion in a Chlorinated Solvent Incinerator
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001046
EISBN: 978-1-62708-214-3
... UNS S30900 Incoloy 800 UNS N08800 Inconel 625 UNS N06625 Inconel 600 UNS N06600 Inconel C-276 UNS N10276 High-temperature corrosion and oxidation Background The thin plates within a type 309 stainless steel chlorinated solvent combustion preheater/heat exchanger showed severe...
Abstract
The thin plates within a type 309 stainless steel chlorinated solvent combustion preheater/heat exchanger designed to process fumes from a solvent coating process showed severe corrosion within 6 months of service. Within a year corrosion had produced holes in the plates, allowing gases to shunt across the preheater/exchanger. Metallographic examination of the plates showed that accelerated internal oxidation had been the cause of failure. Corrosion racks of candidate alloys (types 304, 309, and 316 stainless steels, Inconel 600, Inconel 625, Incoloy 800, Incoloy 825, and Inco alloy C-276) were placed directly in the hot gas stream, containing HCl and Cl2, for in situ testing. Results of this investigation showed that nickel-chromium corrosion-resistant alloys, such as Inconel 600, Inconel 625, and Inco alloy C-276, performed well in this environment. Laboratory testing of the same alloys, along with Inconel alloys 601, 617, and 690 and stainless steel type 347 was also conducted in a simulated waste incinerator nitrogen atmosphere containing 10% Co2, 9% O2, 4% HCl, 130 ppm HBr and 100 ppm SO2 at 595, 705, 815, and 925 deg C (1100, 1300,1500, and 1700 deg F). The tests confirmed the suitability of the nickel-chromium alloys for such an environment. Inconel 625 was selected for fabrication of a new preheater/exchanger.
Book Chapter
Failure of Inconel 600 Thin-Walled Tubes Due to Nitriding
Available to PurchaseSeries: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001676
EISBN: 978-1-62708-229-7
... of Zircaloy-2 and Inconel 600, respectively. Flux detectors Nitridation Nuclear reactor components Tubing Inconel 600 UNS N06600 High-temperature corrosion and oxidation Introduction The self-powered flux detectors presently in use in some nuclear reactors are Pt- or V-cored co-axial...
Abstract
The self-powered flux detectors used in some nuclear reactors are Pt or V-cored co-axial cables with MgO as an insulator and Inconel 600 as the outer sheath material. The detectors are designed to operate in a He atmosphere; to maximize the conduction of heat (generated from the interaction with gamma radiation) and to prevent corrosion. A number of failures have occurred over the years because of a loss of the He cover gas in the assembly. This has resulted in either acid attack on the Inconel 600 sheath in a wet environment or gaseous corrosion in a dry environment. In the latter case, nitriding and embrittlement occurred at temperatures as low as 300 to 400 deg C (determined from an examination of the oxidation of the Zircaloy-2 carrier rod on which the detectors were mounted). Recent results are described and discussed in terms of the oxidation and nitriding kinetics of Zircaloy-2 and Inconel 600, respectively.
Book Chapter
Forms of Corrosion
Available to PurchaseSeries: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003548
EISBN: 978-1-62708-180-1
Abstract
This article addresses the forms of corrosion that contribute directly to the failure of metal parts or that render them susceptible to failure by some other mechanism. It describes the mechanisms of corrosive attack for specific forms of corrosion such as galvanic corrosion, uniform corrosion, pitting and crevice corrosion, intergranular corrosion, and velocity-affected corrosion. The article contains a table that lists combinations of alloys and environments subjected to selective leaching and the elements removed by leaching.
Series: ASM Handbook
Volume: 11
Publisher: ASM International
Published: 15 January 2021
DOI: 10.31399/asm.hb.v11.a0006783
EISBN: 978-1-62708-295-2
Abstract
Corrosion is the electrochemical reaction of a material and its environment. This article addresses those forms of corrosion that contribute directly to the failure of metal parts or that render them susceptible to failure by some other mechanism. Various forms of corrosion covered are galvanic corrosion, uniform corrosion, pitting, crevice corrosion, intergranular corrosion, selective leaching, and velocity-affected corrosion. In particular, mechanisms of corrosive attack for specific forms of corrosion, as well as evaluation and factors contributing to these forms, are described. These reviews of corrosion forms and mechanisms are intended to assist the reader in developing an understanding of the underlying principles of corrosion; acquiring such an understanding is the first step in recognizing and analyzing corrosion-related failures and in formulating preventive measures.
Book Chapter
Failures of Pressure Vessels and Process Piping
Available to PurchaseSeries: ASM Handbook
Volume: 11A
Publisher: ASM International
Published: 30 August 2021
DOI: 10.31399/asm.hb.v11A.a0006812
EISBN: 978-1-62708-329-4
Abstract
This article discusses pressure vessels, piping, and associated pressure-boundary items of the types used in nuclear and conventional power plants, refineries, and chemical-processing plants. It begins by explaining the necessity of conducting a failure analysis, followed by the objectives of a failure analysis. Then, the article discusses the processes involved in failure analysis, including codes and standards. Next, fabrication flaws that can develop into failures of in-service pressure vessels and piping are covered. This is followed by sections discussing in-service mechanical and metallurgical failures, environment-assisted cracking failures, and other damage mechanisms that induce cracking failures. Finally, the article provides information on inspection practices.