Results 141 to 150 of about 523 (178)

Migration and release behavior of tritium in SS316 at ambient temperature

Journal of Nuclear Materials, 2007
Abstract BIXS measurements indicate that immersion into water or chemical etching of SS316 contaminated with tritium at moderate temperatures causes an immediate reduction of the outermost surface concentration of tritium. The fraction of surface tritium removed by water, i.e.
Y. Torikai, D. Murata, R.-D. Penzhorn, K. Akaishi, K. Watanabe, M. Matsuyama   +5 more
openaire   +1 more source

Corrosion–erosion test of SS316 in flowing Pb–Bi

Journal of Nuclear Materials, 2003
Abstract Corrosion tests of austenitic stainless tube were done under flowing Pb–Bi conditions for 3000 h at 450 °C. Specimens were 316SS produced as a tubing form with 13.8 mm outer diameter, 2 mm thickness and 40 cm length. During operation, maximum temperature, temperature difference and flow velocity of Pb–Bi at the specimen were kept at 450, 50 °
K. Kikuchi, Y. Kurata, S. Saito, M. Futakawa, T. Sasa, H. Oigawa, E. Wakai, K. Miura   +7 more
openaire   +1 more source

Reweldability test of irradiated SS316 by the TIG welding method

Journal of Nuclear Materials, 1996
Abstract Stainless steel is a candidate material for the structural material in fusion reactors. Rewelding of irradiated materials will have a large impact on the design and the maintenance of in-vessel components. In the present work, the welding specimens made of type 316 stainless steel were irradiated in JMTR (Japan materials testing reactor) to ...
Kunihiko Tsuchiya, Hiroshi Kawamura, Rokuro Oyamada   +2 more
openaire   +1 more source

Tritium Release from SS316 under Vacuum Condition

Fusion Science and Technology, 2015
Type 316 stainless steel specimens loaded with tritium either by exposure to 1.2 kPa HT at 573 K or submersion into liquid HTO at 298 K showed characteristic thin surface layers trapping tritium in...
Y. Torikai, R.-D. Penzhorn
openaire   +1 more source

Alloys SS316 and Hastelloy-C276 in Supercritical CO2 at High Temperature

Oxidation of Metals, 2015
Commercially available high pressure tubing materials SS316 and Hastelloy-C276, containing a similar chromium content about 17 wt%, were internally pressurised by flowing supercritical CO2 at 20 MPa and heated externally, to 650 °C in the case of SS316, and 650–750 °C in the case of Hastelloy-C276.
R. I. Olivares, D. J. Young, P. Marvig, W. Stein   +3 more
openaire   +1 more source

Combined Numerical and Experimental Approach to Study the Effect of External SS316 Cathode on the Localized Corrosion in AA7050-T7451 Galvanically Coupled with SS316 Under Atmospheric Conditions

ECS Meeting Abstracts, 2016
Connections between dissimilar metal alloys (e.g., aluminum (Al) alloy components and stainless steel (SS) fasteners) are frequently encountered in airframes exposed to an atmospheric marine environment. This exposure results in the formation of thin layer of electrolyte containing chloride species on the materials surface.
Chao Liu, Robert G. Kelly
openaire   +1 more source

Characterization of Friction-Surfaced SS316 Overlaid on Medium-Carbon Steel

Silicon, 2017
In this paper, a study has been done on the solid-state coating of SS316 over medium-carbon steel EN8. The objective is to determine the characterization of friction-surfaced joints with process parameters such as axial load, traverse speed and rotational speed.
R. George Sahaya Nixon, B. S. Mohanty
openaire   +1 more source

Hardening of SS316 Stainless Steel Caused by the Irradiation with Argon Ions

Materials Science, 2016
We study the correlation between the radiation-induced hardening and the evolution of microstructure of SS316 stainless steel irradiated with 1.4 MeV Ar+ ions within the dose range 0–25 dpa at 300 and 900°K. It is shown that the degree of hardening attained under these doses can be as high as 75% and its saturation is observed at 2 dpa. The clusters of
S. A. Karpov, G. D. Tolstolutskaya, B. S. Sungurov, A. Yu. Rostova, G. N. Tolmacheva, I. E. Kopanets   +5 more
openaire   +1 more source

Effect of Neutron Irradiation on Mechanical Properties of Cu-Alloy/SS316 Joints

Fusion Technology, 2001
The effects of neutron irradiation on tensile properties of the Cu alloys to type 316 stainless steel (SS316LN-IG) joints fabricated by friction welding method were examined. Additionally, irradiation tests of Al 2 O 3 -dispersed copper alloy (Al-25) and SS316LN-IG were conducted.
Hirokazu Yamada, Kunihiko Tsuchiya, Masaru Nakamichi, Hiroshi Kawamura   +3 more
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???????????????????????????? ???????????????? ?? ?????????????????????? ?????????????????????? ???????????? SS316

2015
?????????????? ?????????????????????? ???? ?????????????????? ????????????????, ???????????????????????????? ?? ???????????????????? ???????????????????? ?????????? SS316 ???? ???????????????????????? ~ 1 ????.%, ?? ?????????? ?????????? ?????????? ?? ?????????????????????? ???????????????? ???? ???????????? ???????????????????????? ???????????????? ???
openaire   +1 more source