Effects of irradiation on mechanical properties of HIP-bonded reduced-activation ferritic/martensitic steel F82H first wall

Furuya, Kazuyuki; Wakai, Eiichi; Miyamoto, Kenji*; Akiba, Masato; Sugimoto, Masayoshi

Journal of Nuclear Materials, 367-370(1), p.494 - 499, 2007/08

https://doi.org/10.1016/j.jnucmat.2007.03.011

A partial mock-up of a breeding blanket structure made of F82H steel has been successfully fabricated. In this study, microstructural observation and EDX analysis of the HIP interfaces were performed, and effects of irradiation on mechanical properties of the HIP-bonded region were also examined. Neutron irradiation was performed up to about 2 dpa at about 523 K. After the irradiation, tensile test was performed at temperatures of 295 and 523 K. The HIP interfaces possessed many precipitates, and enriched peak spectrum of chromium was detected from the precipitates. In addition, aspect of the spectrum was qualitatively equivalent to that of MC in grain boundaries of F82H steel. In result, the HIP boundary has many MC which were generally seen in grain boundaries of F82H steel. Rupture did not occur in the HIP interface. In result, it can be mentioned that bondability is maintained under the irradiation and testing conditions. The strength and elongation of the HIP-bonded region decreased somewhat in comparison with the results of an IEA standard steel.

The Neutron irradiation effect on mechanical properties of HIP joint material

Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Sato, Satoshi; Mori, Kensuke*

Journal of Nuclear Materials, 335(1), p.33 - 38, 2004/10

https://doi.org/10.1016/j.jnucmat.2004.05.014

no abstracts in English

Development of bonding techniques for cryogenic components, 2; HIP bonding between Cu alloys and Ti, cryogenic stainless steels

Saito, Shigeru; Ouchi, Nobuo; Fukaya, Kiyoshi*; Ishiyama, Shintaro; Tsuchiya, Yoshinori; Nakajima, Hideo

JAERI-Tech 2003-027, 63 Pages, 2003/03

JAERI-Tech-2003-027.pdf:19.84MB

Around the super conducting (SC) coils of SC linear accelerator or fusion reactor, several kind of dissimilar materials bond will be needed. In recent years, pure titanium has been proposed as jacket material for SC coil of fusion reactor. Cu-alloys will be used for connection of SC coils. Cryogenic stainless steels have been development for structural material. Therefore, it is necessary to develop new bonding techniques and we started the bonding technology development by hot isostatic press (HIP) method to bond Cu-alloys with titanium and cryogenic stainless steels. In this experiments, optimization of HIP bonding condition and evaluation of bonding strength by metallurgical observation, tensile and bending tests were performed.

Deveopment of bonding techniques for cryogenic components, 1; HIP bonding tests between Ti and cryogenic stainless steels

Saito, Shigeru; Ouchi, Nobuo; Ishiyama, Shintaro; Tsuchiya, Yoshinori*; Nakajima, Hideo; Fukaya, Kiyoshi*

JAERI-Tech 2002-048, 68 Pages, 2002/05

JAERI-Tech-2002-048.pdf:7.86MB

no abstracts in English

Optimization of HIP bonding conditions for ITER shielding blanket/first wall made from austenitic stainless steel and dispersion strengthened copper alloy

Sato, Satoshi; Hatano, Toshihisa; Kuroda, Toshimasa*; Furuya, Kazuyuki; Enoeda, Mikio; *; Takatsu, Hideyuki

Journal of Nuclear Materials, 258-263, p.265 - 270, 1998/00

https://doi.org/10.1016/S0022-3115(98)00360-2

no abstracts in English