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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
.... 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.c9001343
EISBN: 978-1-62708-215-0
... stainless steel be kept rust free. Cooling systems Marine environments Nuclear reactor components Pipe, corrosion Rusting Water cooling 304 UNS S30400 Stress-corrosion cracking Selected Reference • Warke W. R. , Stress-Corrosion Cracking , Failure Analysis and...
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 Selected Reference • Fatigue Failures, Failure Analysis and Prevention , Vol 11 , ASM Handbook , ASM International , 2002 , p 700 – 727 10.31399/asm.hb.v11.a0003544 During a...
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 Selected Reference...
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
... were 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.c9001329
EISBN: 978-1-62708-215-0
... Leakage Nuclear reactor components Welded joints ASME SB148 C95200 UNS C95200 C95400 UNS C95400 Dealloying/selective leaching Selected Reference • Forms of Corrosion , Failure Analysis and Prevention , Vol 11 , ASM Handbook , ASM International , 2002 , p 761 – 795...
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: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001056
EISBN: 978-1-62708-214-3
... circumferential length of the pipe without catastrophic failure. A thin stainless steel sleeve was inserted in the branch pipe to resolve the problem. Fracture mechanics Leakage Nuclear reactor components Piping Thermal fatigue 347 UNS S34700 Thermal fatigue fracture Selected...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001682
EISBN: 978-1-62708-229-7
... 10.31399/asm.hb.v11.a0003540 The Savannah River Site (SRS) has five nuclear material production reactors (C, K, L, P and R) which were designed and built in the early 1950's, at the direct request of President Truman. These low temperature, low pressure reactors use heavy water as a neutron moderator...
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...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001695
EISBN: 978-1-62708-229-7
... DOE Reactor Irradiated Nuclear Materials at the Savannah River Site,” Proceedings of Topical Meeting on DOE Spent Fuel , 118 – 124 , Salt Lake ( 1994 ). 2. Howell J.P. , “Corrosion of Aluminum-Clad Spent Fuel in Reactor Basin Water Storage,” NACE Corrosion/95, paper 429, Houston...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001146
EISBN: 978-1-62708-229-7
... Power Company informed the United States Nuclear Regulatory Commission (U.S. NRC) Region II that a crack had been discovered in the vent header of the Edwin I. Hatch Nuclear Plant Unit 2. This notification prompted the U.S. NRC to issue IE Bulletin No. 84-01, “Cracks in Boiling Water Reactor Mark I...
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.c9001676
EISBN: 978-1-62708-229-7
... Zircaloy-2 and Inconel 600, respectively. Flux detectors Nitridation Nuclear reactor components Tubing Inconel 600 UNS N06600 High-temperature corrosion and oxidation References 1. Drewell N. H. , unpublished results. 2. Kumar A. and Raman V...
Series: ASM Failure Analysis Case Histories
Volume: 3
Publisher: ASM International
Published: 01 December 2019
DOI: 10.31399/asm.fach.v03.c9001812
EISBN: 978-1-62708-241-9
... environments in industry Coatings, e.g., Cd, Zn on steels, inadvertently exposed to high temperatures Solders, Brazes, and Galvanizing baths (if applied/residual stresses are high) Liquid–metal coolants for nuclear reactors, nuclear fission products, and neutron spallation targets (Pb-Bi...
Series: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003512
EISBN: 978-1-62708-180-1
..., the first step in the design of any pressure vessel is to select the proper design code based on its intended use. For example, a pressure vessel may be a power or heating boiler, a nuclear reactor chamber, a chemical process chamber, a hydrostatic test chamber used to test underwater equipment, or a...
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
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
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001370
EISBN: 978-1-62708-215-0
... of surface hardening. Service water systems in nuclear reactors serve as a plant heat sink for various important components, such as preheating and emergency cooling, heat exchangers, nitrogen coolers, biological shield heat exchangers, diesel generators, air compressors, chiller condensers...