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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
... cracking (IGSCC) Nuclear power plants Nuclear reactor coolant piping Nuclear Pump seal wear rings Pump shaft cracking Stress corrosion cracking 304 UNS S30400 Cemented carbide Stress-corrosion cracking Dealloying/selective leaching 1. Introduction Approximately 113 nuclear electrical...
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
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...
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.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.c9001326
EISBN: 978-1-62708-215-0
... Abstract Pressure testing of a batch of AISI type 316L stainless steel thermowells intended for use in a nuclear power-plant resulted in the identification of leakage at the tips in 20% of the parts. Radiography at the tip region of representative thermowells showed linear indications along...
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
... included use of a case-hardened En 8 steel with the correct composition and regular maintenance of the pump. Cooling systems Nuclear reactors Shafts (power) Water cooling EN8 Fatigue fracture Corrosion fatigue Background After 7 years of operation, a service water pump in a nuclear...
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
... Abstract Leaks developed at random locations in aluminum brass condenser tubes within the first year of operation of a steam condenser in a nuclear power plant. One failed tube underwent scanning electron microscopy surface examination and optical microscope metallography. It was determined...
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 Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003515
EISBN: 978-1-62708-180-1
... of components important to safety. No one action, system, or component is depended upon to maintain safety; but a number of actions, systems, and components with multiple backups taken together—defense in depth—are responsible for maintaining high reliability and safety of operating nuclear power reactors...
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.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.modes.c9001632
EISBN: 978-1-62708-234-1
... . 10.1016/S0022-3115(01)00517-7 10. Thomas L.E. and Bruemmer S.M. : Proc. of the Eighth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors , Bruemmer S.M. and McIlree A.R. , Ed., American Nuclear Society , 1997 , p. 772 . 11...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001559
EISBN: 978-1-62708-229-7
... cost of all the piping was estimated at over $1,000,000, not including potential cost penalties for delayed startup of the nuclear power plant. Pipe replacement costs were particularly high (approximately $2,000/ft.) due to the necessity to erect scaffolding, extensive welding in potentially...
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
... Abstract Leaks developed in 22 admiralty brass condenser tubes. The tubes were part of a condenser that was being used to condense steam from a nuclear power plant and had been in operation for less than 2 years. Analysis identified three types of failure modes: stress-corrosion cracking...
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
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001146
EISBN: 978-1-62708-229-7
... Abstract A metallurgical failure analysis was performed on pieces of the cracked vent header pipe from the Edwin I. Hatch Unit 2 Nuclear power plant. The analysis consisted of optical microscopy, chemical analysis, mechanical Charpy impact testing, and fractography. It was found...
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
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001695
EISBN: 978-1-62708-229-7
... examination of two Mk-31A target slugs stored in the L-Reactor basin for about 5 years and a summary of results from the corrosion surveillance programs through 1997. Corrosion in the SRS Basins Aluminum-clad spent nuclear fuel has been successfully stored in the P, K, and L-Reactor basins over the 43...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c9001710
EISBN: 978-1-62708-229-7
.... Aluminum cladding Spent nuclear fuel Storage racks 6061 UNS A96061 Exfoliation corrosion Pitting corrosion Introduction Aluminum-clad spent nuclear fuel, irradiated in the reactors at the Savannah River Site (SRS), is stored in concrete lined, water-filled basins located at the individual...