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Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001515
EISBN: 978-1-62708-229-7
... to full-power operation and ensured a low probability of a similar occurrence for all CANDU reactors. Fracture mechanics Laminations Nuclear reactor components Pressure tubes Zr-2.5Nb UNS R60901 Hydrogen damage and embrittlement Mixed-mode fracture Metalworking-related failures...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001343
EISBN: 978-1-62708-215-0
... Abstract A section of type 304 stainless steel pipe from a stand by system used for emergency injection of cooling water to a nuclear reactor failed during precommissioning. Leaking occurred in only one spot. Liquid penetrant testing revealed a narrow circumferential crack. Metallographic...
Image
Published: 15 January 2021
Fig. 45 Schematic of boiling water nuclear reactor. Red arrows identify the jet pumps located between the reactor vessel and the reactor core. Source: Ref 28 More
Book Chapter

Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0091659
EISBN: 978-1-62708-229-7
... heat treated by heating at 885 deg C (1625 deg F) for 24 h and aging at 705 deg C (1300 deg F) for 20 h. Jet pump beams were found to have failed in two nuclear reactors, and other beams were found to be cracked. Investigation (visual inspection, metallurgical examination, tension testing...
Series: 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
... 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...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001370
EISBN: 978-1-62708-215-0
... Abstract A service water pump in a nuclear reactor failed when its shaft gave way. The fracture originated in the threaded portion of the sleeve nut on the drive-end side of the shaft. Results of the failure analysis showed that the cracking initiated at the thread root as a result of corrosion...
Series: 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
... 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...
Book Chapter

By D.R. Diercks
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001536
EISBN: 978-1-62708-229-7
.... Analyses of four failed components from nuclear plants are then described to illustrate the kinds of failures seen in service. The failures discussed are (1) intergranular stress-corrosion cracking of core spray injection piping in a boiling water reactor, (2) failure of canopy seal welds in adapter tube...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001282
EISBN: 978-1-62708-215-0
.... Pickling and passivation resulted in severe pitting because of end-grain effect. Strict control of heat treatment parameters to prevent sensitization and modification of pickling and passivating conditions for machined components were recommended. Breeder reactors Fast nuclear reactors Finishing...
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
... corrosion and propagating by fatigue. The cause of the pitting/cracking was related to the unit's copper species in solution. Boilers Nuclear reactor components Stress-corrosion cracking Welded joints ASTM 302 grade B UNS K12022 Corrosion fatigue Background Two vertical U-tube design...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001571
EISBN: 978-1-62708-229-7
... on the quantification of changes in both the degree of carbide precipitation and delta ferrite content and shape in the cladding as a function of temperature and time to refine the estimates of the maximum temperatures experienced. Delta ferrite Hot cracking Nuclear power reactors Steel plate Weld cladding...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001315
EISBN: 978-1-62708-215-0
.... Breeder reactors Fast reactors Nuclear reactor components Welded joints Welding parameters AM350 UNS S35000 Joining-related failures Background AM350 stainless steel bellows used in the control rod drive mechanism of a fast breeder reactor failed after 1000 h of service in sodium at 550 °C...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001327
EISBN: 978-1-62708-215-0
.... Nuclear reactor components Pipe fittings Weldments ASME SA106-B Corrosion fatigue Background During a refueling outage at a pressurized water reactor (PWR), feedwater reducers to all four steam generators were replaced. Three of the four piping reducers showed indications of flaws when...
Series: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001078
EISBN: 978-1-62708-214-3
... were examined using SEM microscopy. Failure of the gears was attributed to heavy wear resulting from misalignment. A lack of adequate lubrication was also noted. Periodic alignment adjustment and lubrication were recommended. Catastrophic wear Gear teeth Nuclear reactor components Tin bronze...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001350
EISBN: 978-1-62708-215-0
... in service due to vibration of the nozzles during filling and draining of the tank. Breeder reactors Crack propagation Fast nuclear reactors Storage tanks, design 316L UNS S31603 Fatigue fracture Background Upon arrival at the erection site, an AISI type 316L stainless steel tank...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001349
EISBN: 978-1-62708-215-0
... of factors resulted in failure by stress-corrosion cracking. Implementation of a new repair procedure was recommended. Repairs were successfully made using the new procedure, and all cracks in the weld repair zones were eliminated. Domes Heat-affected zone Nuclear reactor components Nuclear reactors...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001334
EISBN: 978-1-62708-215-0
... that the tube failed from crevice corrosion under seawater deposits that had formed on the inner surface. Mechanical cleaning of the condenser tubes every 6 months and installation of intake screens of smaller mesh size were recommended. Aluminum bronzes Nuclear reactor components Seawater environment...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001326
EISBN: 978-1-62708-215-0
... of the CaO was determined to be slag entrapment during the steel making process. It was recommended that the thermowell blanks be ultrasonically tested prior to machining and that the design be modified to make internal pressurization possible. Leakage Nonmetallic inclusions Nuclear reactor...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001387
EISBN: 978-1-62708-215-0
... material, such as nickel, nickel-base alloy, or stainless steel, was recommended. Anodes Electrolytic cells Nuclear reactor components 1010 ASTM A519 MT1010 UNS G10100 Uniform corrosion Background Several electrolysis cells in a heavy-water up-grading plant began malfunctioning because...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.machtools.c0047840
EISBN: 978-1-62708-223-5
... hardness AZ UNS T30102 Metalworking-related failures Fatigue fracture The mandrel shown in Fig. 1 was part of a rolling tool used for mechanically joining two tubes before they were installed in a nuclear reactor. The operation consisted of expanding the end of a zirconium tube into a stainless...