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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:49 Percentile:95.48(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

A Three-dimensional neutronics-thermohydraulics simulation of core disruptive accident in sodium-cooled fast reactor

Yamano, Hidemasa; Tobita, Yoshiharu; Fujita, Satoshi

Nuclear Engineering and Design, 239(9), p.1673 - 1681, 2009/09

 Times Cited Count:11 Percentile:61.73(Nuclear Science & Technology)

The SIMMER-III code is a two-dimensional, multi-velocity-field, multi-phase, multi-component, Eulerian, fluid-dynamics code coupled with a fuel-pin model and a space- and energy-dependent neutron transport kinetics model. Since SIMMER-III is expected to become a standard tool for fast reactor safety analysis with likely application to licensing calculations, the code must be demonstrated to be sufficiently robust and reliable. For this purpose, a systematic assessment program of the code has been conducted in cooperation with European partners. The development of SIMMER-IV has been performed to be a direct extension of SIMMER-III to three dimensions. Recently, the parallelization of SIMMER-IV has been made to allow applications to reactor calculation within available computational resource. A three-dimensional calculation with SIMMER-IV is presented to indicate more realistic accident scenario.

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 1; Corrosion investigation of steels after 800 and 2,000h exposure to sragnant liquid Pb/Bi at elevated temperatures

Georg Muller*; Gustav Schumache*; Alfons Weisenbur*; Annette Heinzel*; Frank Zimmermann*; Furukawa, Tomohiro; Aoto, Kazumi

JNC TY9400 2002-016, 77 Pages, 2002/06

JNC-TY9400-2002-016.pdf:11.29MB

None

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.

Oral presentation

Generation process of yellow phase from borosilicate glass matrix

Miura, Akihiko; Kobayashi, Hidekazu; Ayame, Yasuo; Shiotsuki, Masao; Weisenburger, S.*; Roth, G.*

no journal, , 

no abstracts in English

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