JOPSS - Search Results

Journal Articles

Continuous and discontinuous yielding behaviors in ferrite-cementite steels

Wang, Y.*; Tomota, Yo*; Omura, Takahito*; Gong, W.*; Harjo, S.; Tanaka, Masahiko*

Acta Materialia, 196, p.565 - 575, 2020/09

https://doi.org/10.1016/j.actamat.2020.07.017

Times Cited Count：31 Percentile：90.48(Materials Science, Multidisciplinary)

Journal Articles

Comparison of the corrosion behavior of austenitic and ferritic/martensitic steels exposed to static liquid Pb-Bi at 450 and 550 $^{circ}$ C

Kurata, Yuji; Futakawa, Masatoshi; Saito, Shigeru

Journal of Nuclear Materials, 343(1-3), p.333 - 340, 2005/08

https://doi.org/10.1016/j.jnucmat.2004.07.064

Times Cited Count：72 Percentile：96.95(Materials Science, Multidisciplinary)

In order to study effects of temperature and alloying elements on corrosion behavior in liquid Pb-Bi which will be used for an accelerator driven system (ADS), corrosion tests of various steels were conducted under static liquid Pb-Bi condition. The tests were performed in oxygen-saturated liquid Pb-Bi at 450 $^{circ}$ C and 550 $^{circ}$ C for 3000h. Oxide films were formed during corrosion at 450 $^{circ}$ C and 550 $^{circ}$ C. Corrosion depth of steels decreased at 450 $^{circ}$ C with increasing Cr content of steels. Austenitic stainless steels containing Ni didn't exhibit appreciable dissolution of Ni and Cr at 450 $^{circ}$ C. The thick ferrite layer produced by dissolution of Ni and Cr was found in JPCA and type 316ss at 550 $^{circ}$ C. For this reason the corrosion depth of austenitic stainless steels, JPCA and type 316ss became large. A Si-added austenitic stainless steel showed good corrosion resistance at 550 $^{circ}$ C because a protective oxide film formed on the steel prevented dissolution of Ni and Cr into liquid Pb-Bi.

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.

Journal Articles

Effects of triple ion beams in ferritic/martensitic steel on swelling behavior

Wakai, Eiichi; Sawai, Tomotsugu; Furuya, Kazuyuki; Naito, Akira; Aruga, Takeo; Kikuchi, Kenji; Yamashita, Shinichiro*; Onuki, Somei*; Yamamoto, Shunya; Naramoto, Hiroshi; et al.

Journal of Nuclear Materials, 307-311(Part.1), p.278 - 282, 2002/12

https://doi.org/10.1016/S0022-3115(02)01076-0

Times Cited Count：51 Percentile：93.7(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports