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Nuclear reactor components

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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
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0091659
EISBN: 978-1-62708-229-7
..., reheat treatment, or preload reduction. Boiling water reactors Jet pumps Nuclear reactor components Inconel X-750 UNS N07750 Stress-corrosion cracking Jet pumps, which have no moving parts, provide a continuous circulation path for a major portion of the core coolant flow in a boiling...
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
... that the stainless steel be kept rust free. Cooling systems Marine environments Nuclear reactor components Pipe, corrosion Rusting Water cooling 304 UNS S30400 Stress-corrosion cracking Background A section of 250 mm (10 in.) diam type 304 stainless steel pipe failed during precommissioning...
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
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...
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.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: 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.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: 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: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001074
EISBN: 978-1-62708-214-3
... cavities. Investment castings Materials handling Nuclear reactor components Porosity Radioactive materials Servomechanisms Shrinkage 420 UNS S42000 Casting-related failures Background The yoke body pin of a master slave manipulator, a remote-controlled device used for handling...
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
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001085
EISBN: 978-1-62708-214-3
... crack indication revealed that the failure was caused by hot cracking related to original weld repairs performed on the impeller casting. Castings Nuclear reactor components Repair welding Rotary pumps Weld defects Welded joints CA-15 UNS J91150 Joining-related failures Background...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001351
EISBN: 978-1-62708-215-0
... reactors Leakage Marine environments Nuclear reactor components, corrosion Pitting (corrosion) Welded joints, corrosion Weldments, corrosion 347 UNS S34700 Stress-corrosion cracking Background A number of AISI 347 stainless steel bellows intended for use in the control rod drive mechanism...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001329
EISBN: 978-1-62708-215-0
... Leakage Nuclear reactor components Welded joints ASME SB148 C95200 UNS C95200 C95400 UNS C95400 Dealloying/selective leaching Background Leaks were found in 90 out of 782 aluminum bronze valves and fittings in an essential cooling water (ECW) system at a nuclear power plant. The leakage...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001390
EISBN: 978-1-62708-215-0
... not been carried out as specified. It was recommended that the sheathing material be fully annealed and that the outer surface be pickled and passivated. Electric heating elements Heat-distributing units Marine atmospheres Nuclear reactor components Sheaths 304L UNS S30403 Stress-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
... 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...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001310
EISBN: 978-1-62708-215-0
... was recommended. Crevice corrosion Nuclear reactor components Pitting (corrosion) Transgranular fracture Admiralty brass Stress-corrosion cracking Brittle fracture Background Leaks developed in 22 admiralty brass condenser tubes. Applications The tubes were parts of a condenser...
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...