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Failure analysis of a stainless steel hydrotreating reactor
Engineering Failure Analysis, 2011Abstract This paper presents an analysis of a failed AISI 316L austenitic stainless steel (SS) hydrotreating reactor that produces flavors and fragrances. Pitting and cracking were observed mainly in the vicinity of the circumferential and longitudinal shell welds on the internal surface of the reactor by dye penetrant testing (DPT).
W.B. Kan, H.L. Pan
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Irradiation-Embrittlement of Reactor Pressure Vessel Steel
18th International Conference on Nuclear Engineering: Volume 5, 2010Irradiated for 4 cycles inside the reactor, the irradiation surveillance capsule (ISC) was withdrawn and transported to Nuclear Power Institute of China (NPIC) for dismantling in the hot cell. This paper presented tensile tests and Charpy-V impact tests on non-irradiated and irradiated specimens. Tensile tests were performed at room temperature and 300
Guoyun Li +4 more
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Steels for nuclear reactors: Eurofer 97
2016These days, climate change and its consequences regularly make the news. Sea levels are rising, poles are defrosting, species are becoming extinct, the ozone layer is being destroyed and the earth's temperature is increasing. These symptoms convey a clear call to action: the preservation of the environment needs to be of the highest concern.
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Developing steels for service in fusion reactors
JOM, 1992Steels used in the fusion reactors of the future will be exposed to a high-energy neutron irradiation field at elevated temperatures. To reduce the production of long-lived radioactive isotopes and deleterious mechanical effects, steels are being developed in which certain common alloying elements are eliminated.
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Investigation of Reactor Steels
Materials Science Forum, 2001V. Slugeň +7 more
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ODS ferritic steel for nuclear reactors
2017Oxide dispersion strengthened steels are candidate materials for structural constituents in IV generation fission nuclear reactors and for fusion nuclear reactors. A reduced activation nano-oxide strengthened ferritic steel is produced by mechanical alloying with an average grain size of 400 nm. The steel is produced starting from nanometric powders of
Lovicu G. +6 more
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A Study of the Embrittlement of Reactor Vessel Steel Supports
1985Neutron transport analyses have been done on three standard USA design pressurized water reactors to determine the fluence levels at the vessel supports. The shift in the nil-ductility transition temperature (∆NDTT) at the supports has been estimated directly with the calculated fluence levels in accordance with ASTM Standard E706.
W. C. Hopkins, W. L. Grove
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Single-Pass Through-Reactor Decontamination of N Reactor Carbon Steel Piping
CORROSION 1969, 1969N Reactor, a dual-purpose (both power and plutonium production) pressurized water reactor operated by Douglas United Nuclear, Inc. for the Atomic Energy Commission at the Hanford project, Richland, Washington, started operation in 1964. By 1967, radioactivity deposited in the recirculating primary-system piping and components had increased to the point
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Möossbauer Spectroscopy Used for Testing of Reactor Steels
Czechoslovak Journal of Physics, 2001The main goal in the area of nuclear industry is to increase nuclear safety and reliability of nuclear power plants (NPP). Previous material study was based mainly on experimental data from different destructive testing methods. Modern approach is based more on the non-destructive methods.
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