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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
... Abstract Argonne National Laboratory has conducted analyses of failed components from nuclear power-generating stations since 1974. The considerations involved in working with and analyzing radioactive components are reviewed here, and the decontamination of these components is discussed...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0048814
EISBN: 978-1-62708-229-7
.... Copper ions in solution should be eliminated or minimized. Chlorides Nuclear power generation Pressure vessels Welded joints ASME SA302-8 Stress-corrosion cracking A small leak was found in a nuclear steam-generator vessel constructed of 100-mm (4-in.) thick SA302, grade B, steel [0.25% C...
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
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001326
EISBN: 978-1-62708-215-0
... components Pinhole Thermocouples 316L UNS S31603 (Other, general, or unspecified) corrosion Background A batch of AISI type 316L stainless steel thermowells ( Fig. 1 ) was procured for a nuclear power plant to house thermocouples at 612 locations. Pressure testing revealed that about 20...
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
... a thermal shock in the pipe which, when cooled below its NDTT, cracked in a brittle manner. Low temperature Nil ductility transition temperature Nuclear power generation Piping Thermal shock ASTM A516 grade 70 UNS K02700 Brittle fracture Introduction On February 3, 1984, Georgia Power...
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 power plants. The location of the large, single crack at the counterbore was similar to that observed at other PWRs. This crack and the smaller cracks exhibited crack arrests and a tight oxide film. The nature of the nozzle/reducer area of the steam generator was such that the mean stress...
Series: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001044
EISBN: 978-1-62708-214-3
... Stress-corrosion cracking C44300 UNS C44300 Stress-corrosion cracking Mixed-mode fracture Background Inhibited admiralty brass (UNS C44300) condenser tubes failed during testing. Applications The condenser was part of a repowering project in which an uncompleted nuclear power plant...
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 Handbook
Volume: 11
Publisher: ASM International
Published: 15 January 2021
DOI: 10.31399/asm.hb.v11.a0006796
EISBN: 978-1-62708-295-2
... Power Generation Conf. , 1987 , Pwr-35 59. Keck R.G. and Griffith P. , “ Prediction and Mitigation of Erosion-Corrosive Wear in Secondary Piping Systems of Nuclear Power Plants ,” NUREG/CR-5007, 1987 60. McClintock F.A. and Argon A.S. , Mechanical Behavior...
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
.... Oxygen is a strong influencing factor in the general corrosion of carbon steels in nuclear reactor enviromnents. Oxygen content exerts considerable control on the incubation time of crack growth in A302 grade B material subjected to corrosion fatigue testing. These observations stemmed from a testing...
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 Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003515
EISBN: 978-1-62708-180-1
... down and assembly operations. Similar situations exist in the nuclear power industry, when the inspection interval is linked to other operations such as refueling. There is an obvious motivation to extend the inspection interval. An important objective in the design and operation of structures...
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
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.modes.c9001632
EISBN: 978-1-62708-234-1
... for a variety of experiments in nuclear physics, solid state physics, and neutron science. At LANSCE, for example, a high-power beam of 800 MeV protons at a current level of 1 mA (800 kW) can be transported in vacuum through the experimental area to a beam stop. Because the beam stop must be heavily water...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0091807
EISBN: 978-1-62708-229-7
... Corrosion Cracking Failure of Admiralty Brass Condenser Tubes in a Nuclear Power Plant Cooled by Freshwater , Corros. Sci. Vol 40 ( No. 11 ), 1998 , p 1821 – 1836 10.1016/S0010-938X(98)00079-1 Selected Reference Selected Reference • Warke W. R. , Stress-Corrosion Cracking...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.design.c9001578
EISBN: 978-1-62708-233-4
... height prevented the excitation of the window, and these combined actions solved both the noise and vibration issues. Part II—Turbines, Pumps, and Compressors Case #1: High Vibration on a High Pressure Core Injection Pump at a Nuclear Plant Operators of nuclear power plants are required...
Series: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001079
EISBN: 978-1-62708-214-3
... 1570-2, EPRI Nuclear Power Division, Sept 1989 . 4. Jhansale H.R. and McCann D.R. , Bore Inspection and Life Evaluation of Vintage Steam Turbine/Generator Rotors , ASTM J. Test. Eval. , Vol 18 ( No. 6 ), Nov 1990 , p 446 – 453 . 10.1520/JTE12514J 5. Jhansale H.R...
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...