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Futakawa, Masatoshi; Kurata, Yuji; Henry, J.*; Ioka, Ikuo; Saito, Shigeru; Naito, Akira
FZKA-6876, p.166 - 171, 2003/12
A report at MEGAPIE(Megawatt Pilot Experiment) Technical R & D Meeting is collected into an FZK report. Triple ion beam irradiation tests on T91 specimens were conducted under MEGAPIE condition using TIARA facility at JAERI. Results of triple ion beam irradiation up to 15dpa, 1400appm He, 10000appm H at 320
C were compared with those of single or dual beam irradiation of Fe or He ions by use of a micro-indentation method. Hardsness increase was mainly attributed to displacement damage by Fe ions. A little effect on hardness was found on simultaneous implantation of He and H ions. An analysis method to predict mechanical characterization form micro-indentation test results was developed on ion irradiated materials.
Watanabe, Nao; Sugawara, Takanori; Okubo, Nariaki; Nishihara, Kenji
no journal, ,
no abstracts in English
CKomatsu, Atsushi; Kato, Chiaki
no journal, ,
A corrosion test was conducted in a molten lead-bismuth eutectic alloy having an oxygen concentration of about 10
and 10
wt%. Although the average amount of corrosion of SUS316L was small, localized corrosion became severe when the oxygen concentration decreased. The average amount of corrosion of T91 was larger than that of SUS316L and the amount of corrosion increased slightly as the oxygen concentration increased, but localized corrosion was not severe.
Watanabe, Nao; Nishihara, Kenji; Yoshida, Hiroyuki
no journal, ,
In the design of a reactor using lead-bismuth eutectic (LBE) as a coolant, estimating corrosion rate of structural materials is an important issue in considering safety and the life of the entire structure. Oxide layers formed on the surface of T91 steel have corrosion inhibition effect, however, if they dissolve, corrosion can progress rapidly. Growth and dissolution rates of oxide layers depend on temperature and oxygen concentration, especially under static LBE, a semi-mechanical model of these rates has been developed. However, knowledge of them in flow filed is limited. This study aims to estimate them in flowing LBE by CFD. In this report, results of analysis by ANSYS Fluent code implementing the existing these rates model are described.
Saito, Shigeru; Wakui, Takashi; Tsukada, Manabu*; Yamashita, Naoki; Sano, Naruto; Dai, Y.*; Futakawa, Masatoshi
no journal, ,
Post irradiation examination (PIE) of the MEGAPIE (MEGAwatt Pilot Experiment) project has been performed on the samples allotted to JAEA. In the experiments, specimens for tensile test are prepared by taking from the component of the MEGAPIE target such as the beam window (BW) of T91. The irradiation temperatures were about 250 C and the displacement-damage levels ranged between 0.75 and 1.74 dpa. After the tensile tests, SP specimens are prepared from the grip part of the tested tensile specimens. Testing temperatures for SP tests ranged from -150C to 250C. From the area of the load-displacement curves (LDC) of the SP tests, ductile-brittle transition temperature (DBTT) was evaluated. Comparison of these data with previous STIP data showed similar values. In addition, the yield stress and ultimate tensile strength were calculated from the SP tests results by applying the conversion equation. These were compared with the results of the tensile tests and found to be in good agreement.
Komatsu, Atsushi; Saito, Shigeru; Obayashi, Hironari; Kita, Satoshi*; Igarashi, Takahiro
no journal, ,
Corrosion tests were conducted on SUS316L and T91 in molten lead-bismuth eutectic (LBE) alloy under flow with oxygen concentration of 10
wt% to investigate the effects of pre-oxidation (steam oxidation and oxidation in oxygen-saturated LBE) on corrosion. The corrosion inhibition effect was observed for both pre-oxidation treatments, and the corrosion inhibition effect increased when these pre-oxidation treatments were combined.