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JAEA Reports

Report of Examination of the Sample from Core Shroud (2F2-H3) at Fukushima Dai-ni Power Station Unit-2 (Contract research)

The Working Team for Examination of the Sample from Core Shrouds and Primary Loop Recirculation Pipi; Nakajima, Hajime*; Shibata, Katsuyuki; Tsukada, Takashi; Suzuki, Masahide; Kiuchi, Kiyoshi; Kaji, Yoshiyuki; Kikuchi, Masahiko; Ueno, Fumiyoshi; Nakano, Junichi; et al.

JAERI-Tech 2004-015, 114 Pages, 2004/03

JAERI-Tech-2004-015.pdf:38.06MB

The Tokyo Electric Power Company (TEPCO) visually inspected the weld joint of core shroud at Fukushima Dai-ni Nuclear Power Station Unit-2 by a direction of the Nuclear and Industrial Agency, cracks were observed at outer side of the ring weld joint (H3) between a core shroud middle trunk and a middle ring. TEPCO has conducted a material examination with Nippon Nuclear Fuel Development Co. Ltd. (NFD) on the specimen including cracks sampled from the core shroud. The present examination has been performed with the objective to independently investigate and evaluate the materials by jointly attending the examination with NFD from the planning stage. Based on results of the present examination, the probable presence of tensile residual stress by welding process and dissolved oxygen contents in the cooling water, it was shown that the cracks were considered to be stress corrosion cracking (SCC). However, the cause of the cracks needs more consideration on the way of shroud construction.

JAEA Reports

Study on the stress corrosion cracking of zirconium in nuclear fuel reprocessing environment

Kato, Chiaki

JAERI-Research 2003-013, 143 Pages, 2003/08

JAERI-Research-2003-013.pdf:22.12MB

This study is investigation about stress corrosion cracking (SCC) of zirconium in nuclear fuel reprocessing. Chapter 1 is described background. Chapter 2 is explained experimental apparates. Chapter 3 is described the increased oxidization potential on the heat-transfer surface and suggested the initiation of SCC on a boiling heat-transfer surface. Chapter 4 is described that the SCC susceptibility increased with increasing nitric acid concentration and solution temperature on notched specimen by SSRT. In addition, the SCC susceptibility effected by the crystal anisotropy by the hot rolling direction and increased on a parallel face to the rolling direction. Chapter 5 is described that the SCC susceptibility increased in HAZ/base metal boundary in order to the preferential orientation of cleavage plane (0002). Chapter 6 is described that the increased oxidization potential on the heat-transfer surface is attributed to the reduction of nitrous acid concentration by the thermal decomposition on the surface and the removal of the decomposition product from solution by boiling bubbles.

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

JSME International Journal, Series A, 45(1), p.104 - 109, 2002/01

no abstracts in English

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.93 - 99, 2001/06

no abstracts in English

JAEA Reports

Study on development of filler metal for Ni-Cr-W superalloy (Joint research)

Saito, T.*; ; Takatsu, T.*; Tsuji, Hirokazu; Shindo, Masami; Nakajima, Hajime

JAERI-Research 99-036, 99 Pages, 1999/05

JAERI-Research-99-036.pdf:29.53MB

no abstracts in English

Journal Articles

Creep properties of base metal and welded joint of Hastelloy XR produced for high-temperature engineering test reactor in simulated primary coolant helium

Kurata, Yuji; *; *; Tsuji, Hirokazu; *; Shindo, Masami; Suzuki, Tomio

Journal of Nuclear Science and Technology, 36(12), p.1160 - 1166, 1999/00

 Times Cited Count:6 Percentile:46.57(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Trial fabrication of heavy section base metals and welded joints for ITER TF coil

*; Nakajima, Hideo; Nunoya, Yoshihiko; Miura, Yushi; Kawasaki, T.*; Tsuji, Hiroshi

Advances in Cryogenic Engineering Materials, 44, p.73 - 80, 1998/00

no abstracts in English

JAEA Reports

Creep rupture properties of trial welded joints of a Ni-Cr-W superalloy in air environment

; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

JAERI-Research 97-032, 20 Pages, 1997/05

JAERI-Research-97-032.pdf:1.78MB

no abstracts in English

Journal Articles

Improvement of creep resistance of a Ni base superalloy and its weld metal by controlling boron content

; *; *; *; Kondo, Tatsuo

Proc.Int.Conf.on Creep, p.97 - 102, 1986/00

no abstracts in English

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