Helium Irradiation Effect on Hydrogen Isotope Permeation in Austenitic Stainless Steel

スポンサーリンク

概要

• 論文の詳細を見る

• Pre- and simultaneous-irradiation effects on the D permeability of Type-316 stainless steel were investigated using a dual ton-beam irradiation facility. In the He pre-irradiation experiment, the relative D permeation rate decreased to about 0.3 under backward He^<++> irradiation and increased to about 3 under forward He^+ irradiation for a He fluence higher than 2×10^<17> He/cm^2. By a numerical analysis, the change in the permeation rate was found to be mainly attributable to a diffusion-constant reduction in the He-implanted region. In a simultaneous D^+ and backward He^<++> irradiation experiment, a rapid D permeation rate change occurred, probably due to an instantaneously induced D diffusion barrier in addition to the gradual change of the permeation rate similar to that shown in the He backward pre-irradiation experiment.

• 社団法人応用物理学会の論文
• 1986-07-20

著者

• Terasawa Mititaka

  Faculty Of Engineering Himeji Institute Of Technology

• Terasawa Mititaka

  Toshiba Nuclear Engineering Laboratory Toshiba Corporation

• FUKUSHIMA Kimichika

  Toshiba Research and Development Center, Toshiba Corporation

• NAKAHIGASHI Sigeo

  Toshiba Nuclear Engineering Laboratory, Toshiba Corporation

• EBISAWA Katsuyuki

  Nuclear Energy Group, Toshiba Corporation

• IIMURA Masashi

  Toshiba Nuclear Engineering Laboratory, Toshiba Corporation

• Iimura Masashi

  Toshiba Nuclear Engineering Laboratory Toshiba Corporation

• Fukushima Kimichika

  Toshiba Corporation

• Fukushima Kimichika

  Toshiba Research And Development Center Toshiba Corporation

• Nakahigashi Sigeo

  Toshiba Nuclear Engineering Laboratory Toshiba Corporation

• Ebisawa Katsuyuki

  Nuclear Energy Group Toshiba Corporation

• TERASAWA Mititaka

  Toshiba Nuclear Engineering Laboratory

関連論文

• Characterization of Hard Diamond-Like Carbon Films Formed by Ar Gas Cluster Ion Beam-Assisted Fullerene Deposition
• Optical Thin Film Formation with O_2 Cluster Ion Assisted Deposition
• Microstructures and Corrosion Resistance of Magnesium Implanted with Nitrogen Ions
• Helium Irradiation Effect on Hydrogen Isotope Permeation in Austenitic Stainless Steel
• ICONE11-36282 CONCEPTUAL DESIGN OF LOW-TEMPERATURE HYDROGEN PRODUCTION AND HIGH-EFFICIENCY NUCLEAR REACTOR TECHNOLOGY
• Conceptual Design of Low-Temperature Hydrogen Production and High-Efficiency Nuclear Reactor Technology(International Conferences on Power and Energy System)
• Development of a Nuclear Hydrogen Production System by Dimethyl Ether (DME) Steam Reforming and Related Technology
• Void swelling in solution treated, 20% cold-worked and 20% cold-worked+aged Ti-modified 316 steel.
• Electronic States of Zn in GaAs and a Consideration on Its Anomalous Diffusion Phenomena
• Swelling of type 304 stainless steel bombarded with 200keV C+ ions.

スポンサーリンク