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Journal Articles

Mechanical properties of weldments using irradiated stainless steel welded by the laser method for ITER blanket replacement

Yamada, Hirokazu*; Kawamura, Hiroshi; Nagao, Yoshiharu; Takada, Fumiki; Kono, Wataru*

Journal of Nuclear Materials, 355(1-3), p.119 - 123, 2006/09

 Times Cited Count:3 Percentile:25.6(Materials Science, Multidisciplinary)

In this study, the bending properties of welding joint of irradiated material and un-irradiated material (irradiated/un-irradiated joints) were investigated using SS316LN-IG, which is the candidate material for the cooling pipe of ITER. The results of this study showed that the bending position of joints using un-irradiated material was un-irradiated part and that the bending position of irradiated/irradiated joints was fusion area or HAZ (heat affected zone). Although the bending position of joints was different bor the combination pattern between irradiated and un-irradiated materials, the bending strength of joint was almost same. Additionally, it is confirmed that bending strength did not depend on the combination pattern between the irradiated and un-irradiated materials, nor on the relationship between the heat input direction and the bending load direction.

Journal Articles

Manufacturing study and trial fabrication of radial plate for ITER toroidal field coil

Abe, Kanako*; Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*

IEEE Transactions on Applied Superconductivity, 16(2), p.807 - 810, 2006/06

 Times Cited Count:11 Percentile:53.12(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Effects of nitrogen on the mechanical properties of 316LN stainless steels

Ishio, Kotaro*; Nakajima, Hideo

Tetsu To Hagane, 92(2), p.90 - 96, 2006/02

no abstracts in English

Journal Articles

Effects of Nitrogen, Niobium, Phosphorous and Carbon on the mechanical properties of aged 316LN stainless steels at the cryogenic temperature, 4K

Ishio, Kotaro*; Hamada, Kazuya; Nakajima, Hideo

Tetsu To Hagane, 92(1), p.30 - 35, 2006/01

no abstracts in English

Journal Articles

The Effect of neutron irradiation on mechanical properties of YAG laser weldments using previously irradiated material

Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Takada, Fumiki; Nishikawa, Masahiro*

Journal of Nuclear Materials, 340(1), p.57 - 63, 2005/04

 Times Cited Count:4 Percentile:32.08(Materials Science, Multidisciplinary)

This study was performed to clear the effect of neutron re-irradiation on mechanical properties to welding material un-irradiated and irradiated stainless steel. The effect of re-irradiation to these weldaments were evaluated by tensile tests, metallographical observation and hardness test. The result of tensile tests shows that ultimate tensile strength of all joints specimen were almost similar, 0.2% yield strength and total elongation were depend on the irradiation damage and weldaments or not. Therefore, fracture mechanism was not change by re-irradiation. However, brittlement of material was depend on irradiation damage and the property of deformation was sensitive by the effect of irradiation damage or the effect of welding heat.

Journal Articles

Characterization of 316L(N)-IG SS joint produced by hot isostatic pressing technique

Nakano, Junichi; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Nemoto, Yoshiyuki; Tsuji, Hirokazu; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part2), p.1568 - 1572, 2002/12

 Times Cited Count:12 Percentile:62.82(Materials Science, Multidisciplinary)

Type 316LN stainless steel of the international thermonuclear experimental reactor (ITER) Grade (316LN-IG SS) is being considered for the first wall/ blanket component. Hot isostatic pressing (HIP) technique is expected for the fabrication of module. To evaluate the integrity and susceptibility to stress corrosion cracking (SCC) of HIPed 316LN-IG SS, tensile tests in vacuum and slow strain rate tests (SSRT) in high temperature water were performed. Specimen with the HIPed joint shows no deterioration of the tensile strength and susceptibility to SCC in oxygenated water. Thermally sensitized specimen with the HIPed joint was low susceptible to SCC in creviced environment. It is concluded that the strength at joint location is as high as that at the base alloy and the joint interface appears integrity.

Journal Articles

Compatibility between Be$$_{12}$$Ti and SS316LN

Kawamura, Hiroshi; Uchida, Munenori*; Shestakov, V.*

Journal of Nuclear Materials, 307-311(Part1), p.638 - 642, 2002/12

 Times Cited Count:18 Percentile:74.81(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Integral activation experiment on SS-316LN and F82H steel irradiated with d-Be neutron source

Maekawa, Fujio; Wada, Masayuki*; Ikeda, Yujiro; U.Moellendorff*; H.Tsige-Tamirat*

Fusion Technology 1998, 2, p.1465 - 1468, 1998/00

no abstracts in English

Journal Articles

Selection of jacket materials for Nb$$_{3}$$Sn superconductor

F.M.G.Wong*; N.A.Mitchell*; R.L.Tobler*; M.M.Morra*; R.G.Ballinger*; Nakajima, Hideo

Fusion Technology 1996, 0, p.1115 - 1118, 1997/00

no abstracts in English

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