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Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001333
EISBN: 978-1-62708-215-0
... reaction within the tube) and then fractured, which allowed molten salt to flow into the tube. Chemical processing industry Chemical reactors Fused salts, environment Overheating Tubing St 35.8 High-temperature corrosion and oxidation Background A low-carbon steel (St35.8) tube...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.modes.c0047879
EISBN: 978-1-62708-234-1
... to be martensitic as the fusion line was approached. The forged steel shaft was concluded to have failed by ductile fracture and possible reasons were discussed. Corrective measures adopted in the replacement shaft were specified. Agitators Chemical reactors Nuts (fasteners) O-ring seals 316 UNS S31600...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0090881
EISBN: 978-1-62708-229-7
... supported the conclusion that that the deposits formed at locations that experienced steam blanketing or dryout at the higher levels of the steam generators. Recommendations included steam generator water-chemistry controls, chemical cleaning, and reduction of the primary reactor coolant system temperature...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.chem.c0046953
EISBN: 978-1-62708-220-4
... deg F), which exceeded normal operating temperatures, and carburization was not the principal cause of failure. No recommendations were made. Chemical reactors Melting Overheating Hastelloy X UNS N06002 (Other, miscellaneous, or unspecified) failure A portion of the wall of a reactor...
Series: ASM Failure Analysis Case Histories
Volume: 3
Publisher: ASM International
Published: 01 December 2019
DOI: 10.31399/asm.fach.v03.c9001828
EISBN: 978-1-62708-241-9
...Abstract Abstract A heat transport pump in a heavy water reactor failed (exhibiting excessive vibration) during a restart following a brief interruption in coolant flow due to a faulty valve. The pump had developed a large crack across the entire length of a bearing journal. An investigation...
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 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.c0091528
EISBN: 978-1-62708-229-7
...Abstract Abstract A 150 mm (6 in.) schedule 80S type 304 stainless steel pipe (11 mm, or 0.432 in., wall thickness), which had served as an equalizer line in the primary loop of a pressurized-water reactor, was found to contain several circumferential cracks 50 to 100 mm (2 to 4 in.) long. Two...
Series: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001108
EISBN: 978-1-62708-214-3
... that hot bending be used for fabrication of the curved parts. A change of alloy to a low-alloy chromium-molybdenum allay to protect against heat was also suggested. Chemical processing equipment Chemical reactors Creep (materials) Pipe bends Tubing Incoloy 800H UNS N08810 Intergranular...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001280
EISBN: 978-1-62708-215-0
... was aided by internal carburization. Quality control of welding procedures and filler metal was recommended. Chemical processing equipment Chemical processing industry Chemical reactors Crack propagation Furnaces Heat-resistant steels Tubing Weld defects Welded joints HK-40 UNS J94204...
Series: ASM Failure Analysis Case Histories
Volume: 1
Publisher: ASM International
Published: 01 December 1992
DOI: 10.31399/asm.fach.v01.c9001063
EISBN: 978-1-62708-214-3
... tubes of a type 316 stainless steel shell-and-tube condenser leaked unexpectedly in an organic chemical plant. A shell-and-tube condenser is fixed vertically on top of a jacketed reactor that produces vinyl acetate monomer (VAM). The VAM vapor enters the tube side at the bottom of the condenser...
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
.... , and Wood C.J. , “Development of LOMI Chemical Decontamination Technology,” Electric Power Research Institute Report EPRI NP-3177, July 1983 3. Shaw R.A. and Naughton M.D. , in Proc. Second Int. Conf. on Water Chemistry of Nuclear Reactor Systems , Bournemouth, UK , British...
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
...Abstract Abstract A number of AISI 347 stainless steel bellows intended for use in the control rod drive mechanism of a fast breeder reactor were found to be leaking before being placed in service. The bellows, which had been in storage for one year in a seacoast environment, exhibited a leak...
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
...Abstract Abstract A service water pump in a nuclear reactor failed when its shaft gave way. The fracture originated in the threaded portion of the sleeve nut on the drive-end side of the shaft. Results of the failure analysis showed that the cracking initiated at the thread root as a result...
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
...Abstract Abstract Two AISI type 316 stainless steel components intended for use in a reducer section for sodium piping in a fast breeder test reactor were found to be severely corroded—the first soon after pickling, and the second after passivation treatments. Metallographic examination...
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
... Symposium Series No. 293, American Chemical Society , Washington , 1986 , 2 – 25 . 10.1021/bk-1986-0293.ch001 2. Broughton J. M. et al. , Nuclear Technology , August 1989 , 87 , 34 – 53 . 10.13182/NT89-A27637 3. Three Mile Island Reactor Pressure Vessel Investigation...
Series: ASM Handbook
Volume: 11
Publisher: ASM International
Published: 15 January 2021
DOI: 10.31399/asm.hb.v11.a0006785
EISBN: 978-1-62708-295-2
... for the development of season-cracks” ( Ref 3 ), and, in the case of cartridge brass, it was determined that this agency was an environment that contained ammonia. It was concluded that season cracking was the result of the chemical composition of the metal, specifically the amount of zinc in the brass alloy...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.chem.c0048840
EISBN: 978-1-62708-220-4
...Abstract Abstract A spherical carbon steel fixed-catalyst bed reactor, fabricated from French steel A42C-3S, approximately equivalent to ASTM A201 grade B, failed after 20 years of service while in a standby condition. The unit was found to contain primarily hydrogen at the time of failure...
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
...Abstract Abstract This paper describes the analysis of the failure of a Zr-2.5Nb pressure tube in a CANDU reactor. The failure sequence was established as: (1) the existence of an undetected manufacturing flaw in the form of a lamination, (2) in-service development of the flaw by oxidation...
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
...Abstract Abstract Type 347 stainless steel moderator circuit branch piping in a pressurized hot water reactor was experiencing frequent leakage. Investigation of the problem involved failure analysis of leaking pipe specimens, analytical stress analysis, and determination of “leak-before-break...
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
...Abstract Abstract Three ASME SA106 grade B carbon steel feed water piping reducers from a pressurized water reactor showed indications of flaws near welds during ultrasonic testing. Further examination and testing indicated that the cracks resulted from a low-cycle corrosion fatigue phenomenon...