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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.c9001536
EISBN: 978-1-62708-229-7
... is discussed. 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...
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 Visual Examination of General Physical Features Testing Procedure and Results Discussion...
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
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: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001315
EISBN: 978-1-62708-215-0
... failures. Breeder reactors Fast reactors Nuclear reactor components Welded joints Welding parameters AM350 UNS S35000 Joining-related failures Background Visual Examination of General Physical Features Testing Procedure and Results Discussion Conclusion and Recommendations...
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 Visual Examination of General Physical Features Testing Procedure and Results Discussion Conclusion Acknowledgments Selected Reference Selected Reference • Fatigue Failures, Failure...
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
... zones 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...
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
.... It was determined 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...
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
... of localized 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 Visual Examination...
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.c9001351
EISBN: 978-1-62708-215-0
.... Breeder reactors Fast reactors Leakage Marine environments Nuclear reactor components, corrosion Pitting (corrosion) Welded joints, corrosion Weldments, corrosion 347 UNS S34700 Stress-corrosion cracking Background Testing Procedure and Results Discussion Conclusion...
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
... the main 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: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001074
EISBN: 978-1-62708-214-3
... shrinkage cavities. Investment castings Materials handling Nuclear reactor components Porosity Radioactive materials Servomechanisms Shrinkage 420 UNS S42000 Casting-related failures Background Testing Procedure and Results Discussion Conclusion and Recommendations Selected...
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
.... This combination 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...
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 Experimental Results Discussion Conclusions Acknowledgments References References 1...
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
... valves Leakage Nuclear reactor components Welded joints ASME SB148 C95200 UNS C95200 C95400 UNS C95400 Dealloying/selective leaching Background Visual Examination of General Physical Features Testing Procedure and Results Discussion Conclusion and Recommendations...
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
...-resistant 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 Visual Examination of General Physical Features Testing Procedure and Results...
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
... conditions was recommended. Crevice corrosion Nuclear reactor components Pitting (corrosion) Transgranular fracture Admiralty brass Stress-corrosion cracking Brittle fracture Background Visual Examination of General Physical Features Testing Procedure and Results Discussion...