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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.c9001315
EISBN: 978-1-62708-215-0
... Abstract AM350 stainless steel bellows used in the control rod drive mechanism of a fast breeder reactor failed after 1000 h of service in sodium at 550 deg C (1020 deg F). Helium leak testing indicated that leaks had occurred at various regions of the welded joints between the convolutes...
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 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 rate...
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 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 revealed...
Series: ASM Failure Analysis Case Histories
Volume: 2
Publisher: ASM International
Published: 01 December 1993
DOI: 10.31399/asm.fach.v02.c9001350
EISBN: 978-1-62708-215-0
... Abstract Upon arrival at the erection site, an AISI type 316L stainless steel tank intended for storage of fast breeder test reactor coolant (liquid sodium) exhibited cracks on its shell at two of four shell/nozzle fillet-welded joint regions. The tank had been transported from the manufacturer...
Series: ASM Failure Analysis Case Histories
Publisher: ASM International
Published: 01 June 2019
DOI: 10.31399/asm.fach.power.c0048850
EISBN: 978-1-62708-229-7
... identified as CREPLACYL and with material data taken from the Liquid Metal Fast Breeder Reactor Materials Handbook (U.S. Department of Energy). The resultant elastic/plastic/creep deformation analysis indicated that a severe thermal downshock could explain the pattern and that one or more downshocks...
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
... study, Experimental Breeder Reactor II (EBR II). 12 Although there is scatter, the results from materials irradiated by protons are qualitatively similar. In Fig. 24 it is seen that samples irradiated in EBR II retain ductility better than those irradiated with protons. This difference generally...
Series: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0001818
EISBN: 978-1-62708-180-1
Series: ASM Handbook
Volume: 11A
Publisher: ASM International
Published: 30 August 2021
DOI: 10.31399/asm.hb.v11A.a0006812
EISBN: 978-1-62708-329-4
Book Chapter

Series: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003562
EISBN: 978-1-62708-180-1
.... , Fretting in Aqueous Media, Particularly of Roping Steels in Seawater , Wear , Vol 106 , 1985 , p 225 – 260 81. Lewis M.W.J. and Campbell C.S. , Fretting and Wear of Stainless and Ferritic Steels in Liquid-Metal Fast Breeder Reactor Steam Generators , Nucl. Technol. , Vol 55...
Series: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003553
EISBN: 978-1-62708-180-1
... section that led to a caked-on buildup. Dimensions given in millimeters (inches). (b) Extensive SCC into the 317 plate on the inner surface. (c) Close-up view of the cracks with the classic branched appearance of SCC Fig. 34 Cross section through recirculation inlet nozzle of reactor vessel...