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Journal Articles

Oxidation behaviour of P122 and a 9Cr-2W ODS steel at 550$$^{circ}$$C in oxygen-containing flowing lead-bismuth eutectic

Schroer, C.*; Konys, J.*; Furukawa, Tomohiro; Aoto, Kazumi

Journal of Nuclear Materials, 398(1-3), p.109 - 115, 2010/03

 Times Cited Count:45 Percentile:95.32(Materials Science, Multidisciplinary)

The long-term performance of P122 and ODS steel was tested in oxygen-containing flowing lead-bismuth eutectic at 550 $$^{circ}$$C and a flow velocity of 2 m/s by means of exposure experiments in the CORRIDA loop of FZK. The target for the enrichment of dissolved oxygen was a concentration, c$$_{o}$$, of 10$$^{-6}$$mass%. Owing to initial problems in controlling c$$_{o}$$, some of the exposed specimens experienced varying conditions, which allowed for investigating the influence of temporarily low c$$_{o}$$ (down to 10$$^{-9}$$mass%), in addition to constantly high c$$_{o}$$ (averaging 1.6$$times$$10$$^{-6}$$mass%). Maximum exposure times at constantly high c$$_{o}$$ were 10,000 and 20,000 h for P122 and the ODS steel, respectively. Under the testing conditions, both steels were affected by moderate oxidation resulting in the formation of a compact layer of a spinel-type oxide on the surface and a more or less pronounced internal oxidation zone. The thickness of the oxide scale was quantified and used for determining the material loss. For c$$_{o}$$ = 10$$^{-6}$$mass%, logarithmic and power rate laws were fitted to the obtained data as a basis for predicting the metal recession at times exceeding the experimental exposure times.

Journal Articles

Status of development of functional materials with perspective on beyond-ITER

Shikama, Tatsuo*; Knitter, R.*; Konys, J.*; Muroga, Takeo*; Tsuchiya, Kunihiko; M$"o$slang, A.*; Kawamura, Hiroshi; Nagata, Shinji*

Fusion Engineering and Design, 83(7-9), p.976 - 982, 2008/12

 Times Cited Count:35 Percentile:91.33(Nuclear Science & Technology)

Functional materials should play an important role not only in ITER but also in fusion machines beyond ITER, though it is occasionally claimed that future fusion plants should have much more simple structures and they should be free from auxiliary systems such as diagnostics. Studies on test blanket modules (TBM) clearly show the importance of functional materials there. The paper will review the present status of studies and developments of functional ceramics for nuclear fusion applications, with a perspective on their application in electric-power generating fusion power plant, namely DEMO.

Journal Articles

Corrosion behavior of high chromium alloys in flowing LBE at 550$$^{circ}$$C under active oxygen control

Furukawa, Tomohiro; Konys, J.*; M$"u$ller, G.*; Aoto, Kazumi

Namari Bisumasu Riyo Gijutsu Handobukku (CD-ROM), 21 Pages, 2007/03

A key problem in the development of heavy liquid metal cooled fast breeder reactors is corrosion of structural and fuel cladding materials with the coolants, lead-bismuth eutectic (LBE). The present study covers corrosion test on high chromium alloys (P122 steel and ODS steel), performed in flowing LBE at 550$$^{circ}$$C for 800, 2,000 and 5,000h under active oxygen control.

JAEA Reports

Study on Pb-Bi Corrosion of Structural and Fuel Cladding Materials for Nuclear Applications; Part VI. Results of Exposure Experiments in Oxygen Containing Flowing LBE at 550$$^{circ}$$C for 10,000h

Schroer, C.*; Voss, Z.*; Wedemeyer, O.*; Novotny, J.*; Konys, J.*; Heinzel, A.*; Weisenburger, A.*; M$"u$ller, G.*; Furukawa, Tomohiro; Aoto, Kazumi

JNC TY9400 2005-020, 45 Pages, 2005/08

JNC-TY9400-2005-020.pdf:5.26MB

This report summarises the results of exposure experiments on the behaviour of 12Cr-2W steel P122 and an 9Cr-2W ODS-steel in oxygen-containing flowing lead-bismuth eutectic (LBE) at 550$$^{circ}$$C, which were performed in the CORRIDA loop at the Karlsruhe Lead Laboratory (KALLA) as part of the collaboration between the Japan Nuclear Cycle Development Institute and the Karlsruhe Research Centre. The duration of these experiments was nominally 800, 2000, 5000 and 10,000 h. Both steels were tested after surface-finishing by turning and after surface alloying with aluminium in the GESA-facility. Owing to initial problems with the enrichment of oxygen in the flowing LBE, the oxygen content considerably varied during most of these experiments, so that the influence of temporary changes in the oxygen content of the LBE could also be investigated. The behaviour of P122 and ODS at permanently high oxygen content was deduced from an experiment for 4990 h at 550$$^{circ}$$C and (c$$_{O}$$ $$approx$$ 5$$times$$10$$^{-7}$$ mass-% or a$$_{PbO}$$ $$approx$$ 10$$^{-3}$$). The results are compared with the findings of exposures to stagnant LBE at 550$$^{circ}$$C and c$$_{O}$$=10$$^{-6}$$ mass-% (COSTA-experiments).

JAEA Reports

Study on Pb-Bi Corrosion of Structural and Fuel Cladding Materials for Nuclear Applications (2); Part II. Exposure of Weld P122 in Oxygen Containing Flowing LBE at 550$$^{circ}$$C for 5,000h

Schroer, C.*; Voss, Z.*; Wedemeyer, O.*; Novotny, J.*; Konys, J.*; Heinzel, A.*; Weisenburger, A.*; M$"u$ller, G.*; Furukawa, Tomohiro; Aoto, Kazumi

JNC TY9400 2005-019, 26 Pages, 2005/08

JNC-TY9400-2005-019.pdf:5.04MB

This report summarises the results of exposure experiments on the behaviour of 12Cr-2W steel P122 joined by multi-run TIG welding in oxygen-containing flowing lead-bismuth eutectic (LBE) at 550$$^{circ}$$C for nominally 800, 2000 and 5000 h. The flow velocity of the LBE and the mean oxygen content were 2 m/s and 5$$times$$10-7 mass-% (aPbO = 10-3), respectively. The influence of surface-alloying with aluminium (GESA-treatment) was also investigated in an exposure experiment for nominally 5000 h. The behaviour of the welded joint is generally comparable to that of P122 (after the standard heat-treatment), both qualitatively and quantitatively. Only few exceptions were observed which probably result from local peculiarities of the specific sample material. After surface alloying with aluminium, no significant oxidation and no liquid metal corrosion occurred in the centre of the specimens (including the weld seam), where the desired high quality of the aluminised layer was achieved.

Journal Articles

Corrosion behavior of high chromium steels in flowing lead-bismuth at 823K underactive oxygen control

Furukawa, Tomohiro; Konys, J.*; M$"u$ller, G.*; Aoto, Kazumi

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13), 0 Pages, 2005/05

Two kind of high chromium martensitic steels named as 12Cr-steel and ODS-M, proposed for use in fast breeder reactors were subjected to corrosion tests in flowing lead bismuth eutectic (LBE) under active oxygen control at 823 K for up to 5,000 hours. The concentration of dissolved oxygen in LBE was controlled by H2/H2O mixture gas bubbling into LBE to keep at 10-6 wt%. However, the oxygen concentration was degreased with increasing of operation time, and temporarily reached below the value necessary for magnetite formation. Then, after 3,300 hours of effective operation time, oxygen concentration was controlled near the target value by periodically adding argon and mixtures of argon and technical air to the H2/H2O mixture gas stream through the oxygen control system. Both steels exposed in LBE under the condition showed approximately the same corrosion behavior. Double-layer structure composed of Fe-Cr spinel and diffusion zone were observed on the surface of the steels exposed for up to 2,000 hours. After 5,000 hours of exposure, it changed to single-structure composed of Fe-Cr spinel. Results of thickness measurement of the oxide layers, the total thickness of oxidized zone was approximately constant during test periods from 800 hours to 5,000 hours. It meant that the steels showed good corrosion resistance under this tested condition. In addition, both erosion and dissolution attack called as liquid metal corrosion were not observed on the all tested specimens.

JAEA Reports

Study on Pb-Bi Corrosion of Structural and Fuel Cladding Materials for Nuclear Applications; Part V. Results of Exposure Experiments in Oxygen Containing Flowing LBE at 550$$^{circ}$$C for 800 and 2000h

Schroer, G.*; Voss, V.*; Wedemeyer, O.*; Novotny, J.*; Konys, J.*; Heinzel, A.*; Weisenburger, A.*; M$"u$ller, G.*; Furukawa, Tomohiro; Aoto, Kazumi

JNC TY9400 2004-023, 37 Pages, 2004/05

JNC-TY9400-2004-023.pdf:12.34MB

Oral presentation

Corrosion behavior of high chromium steels in flowing lead-bismuth, 2

Aoto, Kazumi; Furukawa, Tomohiro; Konys, J.*; M$"u$ller, G.*

no journal, , 

no abstracts in English

Oral presentation

Corrosion behavior of weld joint of high chromium alloy in flowing lead bismuth eutectic under active oxygen control

Furukawa, Tomohiro; Aoto, Kazumi; Konys, J.*; Mueller, G.*

no journal, , 

A key problem in the development of heavy liquid metal cooled fast breeder reactors is corrosion of structural and fuel cladding materials with the coolants, lead-bismuth eutectic (LBE). Authors have been performed corrosion tests of the materials - high-chromium type martensitic steel (12Cr-steel) and oxide dispersion strengthened martensitic type steel (ODS) - in stagnant LBE under the various oxygen concentrations or in flowing LBE under active oxygen control, and investigated the corrosion behavior. In this paper, the corrosion behavior of the 12Cr-steel joined by multi-run TIG welding (weld 12Cr-steel) and its surface alloying with aluminum in flowing LBE under active oxygen control is presented.

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