Results 201 to 210 of about 418,826 (248)

Effect of Deformation and Orientation on SCC of Alloy 690

CORROSION 2009, 2009
Abstract Alloy 690, of various microstructures and types of cold work, was tested in representative pressurized water reactor primary water at 340 and 360 °C. Intergranular cracking was observed on Alloy 690 at constant stress intensity factor (no cycling) and with “gentle” cyclic loading.
Peter L. Andresen, Martin M. Morra, John Hickling, Al Ahluwalia, John Wilson   +4 more
openaire   +1 more source

Comparison of Different Thermal Treatments for Alloy 690

CORROSION 1990, 1990
Abstract Intergranular carbide precipitation reactions are known to increase the resistance of INCONEL* alloys 600 and 690 (UNS N06600 and N06690)to stress corrosion cracking in nuclear steam generator environments. Initially the same thermal treatment used for alloy 600 was applied to alloy 690, i.e., 1300°F (704°C)/15 hrs.
J R Crum, K A Heck, T. M. Angeliu
openaire   +1 more source

Combined effects of hydrogen and thermal aging on Alloy 690

, 2018
Thermally treated nickel-based Alloy 690 is the material of choice for the steam generator tubes of many nuclear power plants. Thermal aging of Alloy 690 has been shown to increase intergranular carbide precipitation and at aging temperatures below 450˚C
Yagodzinskyy, Yuriy, Mouginot, Roman, Malitckii, Evgenii, Hänninen, Hannu, Huotilainen, Caitlin   +5 more
core   +4 more sources

SCC of Alloy 690 in High Temperature Water

CORROSION 2010, 2010
Abstract Various microstructures of Alloy 690 and types of cold work were tested in representative pressurized water reactor primary water at 290 to 360 °C. Intergranular cracking was observed on Alloy 690 at constant stress intensity factor (no cycling) and with “gentle” cyclic loading, but not in every case.
Peter L. Andresen, Martin M. Morra, Al Ahluwalia, John Wilson   +3 more
openaire   +1 more source

INCONEL ALLOY 690

Alloy Digest, 1981
Abstract INCONEL Alloy 690 is a wrought nickel-base alloy with excellent resistance to many corrosive aqueous media and high-temperature atmospheres. It also has high strength, good metallurgical stability, and favorable fabrication characteristics. It has excellent resistance to stress-corrosion cracking in chloride-containing solutions
openaire   +1 more source

Research on M23C6 precipitation of 690 alloy

2014
Precipitation M23C6 of 690 alloy was studied in this paper. Firstly, M23C6 precipitation and evolution of chromium-depleted zone of 690 alloy during TT were studied. Evolution of chromium-depleted zone of 690 alloy was affected markedly by TT.The test results showed that the lowest chromium concentration in chromium-depleted zone raised dramatically ...
Song Zhigang, Feng han, Zheng Wenjie, Zhang Lihong, Ma Mingjuan, Sang Weijun   +5 more
openaire   +1 more source

Constitutive model for nickel alloy 690 (Inconel 690) at various strain rates and temperatures

International Journal of Plasticity, 2016
no ...
Blaizot, Jérôme, Chaise, Thibaut, Nélias, Daniel, Perez, Michel, Cazottes, Sophie, Chaudet, Philippe   +5 more
openaire   +1 more source

Internal oxidation of alloy 690 in hydrogenated steam

Corrosion Science, 2015
Abstract Alloy 690 was exposed to a hydrogenated steam environment at 480 °C and 1 bar, considered to simulate primary water in a pressurized water reactor. The possibility of internal oxidation in Alloy 690 was evaluated and the likely relevance to SCC in primary water is discussed. Initial surface imaging revealed intragranular metallic Ni nodules,
S.Y. Persaud, S. Ramamurthy, R.C. Newman
openaire   +1 more source

New Etching Procedure for Alloy 690 Ein neues Ätzverfahren für die Legierung 690

Practical Metallography, 1998
Alloy 690 for steam generator tubing is now etched in bromine-methanol for the microstructural examination prior to delivery. A number of etching methods have been tested to find an alternative procedure that is highly reproducible, that clearly reveals all grain boundaries and carbides and that does not involve too harmful chemicals.
Agneta Östberg, Johan Frodigh
openaire   +1 more source

Dissolution Mitigation of Alloy 690 By Electrochemical Surface Modification

ECS Meeting Abstracts, 2014
Metal oxide particles and metal ions are released from the inside surface of steam generator (SG) tubes in operating nuclear power plants. These corrosion products are transported into the core, forming a crud on fuel cladding. The composition of the fuel crud consists mainly of nickel ferrite, and it indicates that the primary source is the nickel ...
Kyung Mo Kim, Hee-Sang Shim, Myung Ji Seo, Do Haeng Hur   +3 more
openaire   +1 more source