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JAEA Reports

Study on Pb-Bi Corrosion of Structural and Fuel Cladding Materials for Nuclear Applications (2) -Part I. Stability of Oxide Layer Formed on High-Chromium Steels in LBE under Oxygen Content and Temperature Fluctuation-

M$"u$ller, G.*; Schumacher, G.*; Heinzel, A.*; Weisenburger, A.*; Zimmermann, F.*; Furukawa, Tomohiro; Aoto, Kazumi

JNC TY9400 2005-021, 33 Pages, 2005/08

JNC-TY9400-2005-021.pdf:2.69MB

The behaviour of protective oxide layers on P122 and its welds and of ODS steel is examined under conditions of fluctuating temperatures and oxygen concentrations to simulate hot spot and loss of oxygen control. P122 steel (12Cr) and its welded joints are exposed to LBE at 550$$^{circ}$$C for 4000h with oxygen concentrations changing between 10$$^{-6}$$ and 10$$^{-8}$$wt% every 800h. It is found that like in case of constant oxygen concentration of 10$$^{-6}$$wt% a protective spinel layer was maintained on P122 and also on its welded joint. Experiments with fluctuating temperatures from 550$$^{circ}$$C to 650$$^{circ}$$C and back every 800h yield satisfying corrosion protection up to 4800h only for the GESA treated ODS steel in LBE with 10$$^{-6}$$wt%. Original ODS steel in LBE with 10$$^{-6}$$ and 10$$^{-8}$$wt% oxygen showed local strong dissolution attack after 4800h in agreement with the behaviour of ODS in LBE with a constant temperature of 650$$^{circ}$$C. GESA treated ODS steel does not form stable protective alumina layers under condition of fluctuating temperatures in LBE with 10$$^{-8}$$wt% oxygen.

JAEA Reports

Study on Pb-Bi Corrosion of Structural and Fuel Cladding Materials for Nuclear Applications, 4; Corrosion investigation of steels at 550 and 650$$^{circ}$$C after 800, 2,000 and 5,000 h of exposure to stagnant liquid Pb-Bi containing 10$$^{-4}$$ and 10$$^{-8}$$ wt% of oxygen

Muller, G.*; Schumacher, G.*; Weisenburger, A.*; Heinzel, A.*; Zimmermann, F.*; Furukawa, Tomohiro; Aoto, Kazumi

JNC TY9400 2003-028, 48 Pages, 2004/01

JNC-TY9400-2003-028.pdf:4.51MB

This is the fourth report on the compatibility of structural and fuel cladding materials that has to be investigated for a possible advanced heavy metal cooled reactor system. The first three reports considered the behavior of 316FR, P122 and ODS steels during 800, 2,000, 5,000 and 10,000 h in stagnant LBE between 500 and 650 degrees centigrade containing 10 sup-6 wt% of oxygen. This report describes experiments of 800, 2,000 and 5,000 h duration in liquid Pb-Bi containing 10 sup-4 and 10 sup-8 wt% of oxygen for 316FR, P122 and ODS steels at 550 and 650 degrees centigrade. 1. No significant dissolution attack occurred on 316FR and P122 steels at 550 degrees centigrade with 10 sup-4 wt% oxygen in LBE. They have Protective oxide layers at the surface, like in the experiments with 10 sup-6 wt% oxygen. At the high oxygen concentration (10 sup-4 wt%) thick oxide multilayers develop on 316FR instead of thin spinel layers at 10 sup-6 wt%, in both experiments LBE is enclosed in the oxide layer. With 10 sup-8 at% oxygen in LBE, however, there is no protective scale formation but strong dissolution attack (up to 120 um) occurs at the 316FR specimen.At the P122 only very little dissolution attack ($$<$$2um) is observed at the surface.

JAEA Reports

Study on Pb-Bi Corrosion of Structural and Fuel Cladding Materials for Nuclear Applications,3; Corrosion investigation of steels between 500 and 650$$^{circ}$$C during 10,000 h of exposure to stagnant liquid Pb-Bi containing 10$$^{-6}$$ wt% of oxygen

Muller, G.*; Schumacher, G.*; Weisenburger, A.*; Heinzel, A.*; Zimmermann, F.*; Furukawa, Tomohiro; Aoto, Kazumi

JNC TY9400 2003-026, 58 Pages, 2004/01

JNC-TY9400-2003-026.pdf:2.25MB

This is the third report on the compatibility of structural and fuel cladding materials that has to be investigated for a possible advanced heavy metal cooled reactor system. The first two reports considered the behavior of 316 FR, P122 and ODS steels during 800, 2,000 and 5,000 h in stagnant LBE at 500 - 650$$^{circ}$$C containing 10-6 wt% of oxygen. This report describes the results of all experiments including that of 10,000 h duration. Martensitic steels perform well at 500 and 550$$^{circ}$$C up to the maximal exposure time of 10,000 h, while austenites fail after 5,000 h. At temperatures of 600$$^{circ}$$C and 650$$^{circ}$$C all of the steels fail the earlier the higher the temperature is. Steels with Al - alloying at the surface by the GESA process withstand corrosion up to the maximal exposure time at all of the applied temperatures if it is ensured that the Al - concentration at the surface is in between 8 - 15 wt%.

JAEA Reports

Study on Pb/Bi Corrosion of Structural and Fuel Claddiang Materials for Nuclear Applications; Part2: Corrosion investigation in stagnant liquid Pb/Bi at 500,550,600 and 650 $$^{circ}C$$ after 5000 h of exposure

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

JNC TY9400 2002-023, 28 Pages, 2002/12

JNC-TY9400-2002-023.pdf:1.12MB

This is the second report on the compatibility of structural and fuel cladding materials that has to be investigated for a possible sdvanced heavy metal cooled reactor system. The first report considered the behaviour of 316FR, P122 and ODS steels during 800 and 2000 h in stag-nant LBE at 500 - 600$$^{circ}C$$. This second report describes the continuation of the tests to 5000 h. The results obtained are : 1. Still no attack on all 3 sreela at 500$$^{circ}C$$. They have protective oxide layers at the surface. 2. Starting dissolution attack on ODS and P122 but not on 316FR at 500$$^{circ}C$$. 3. At 600$$^{circ}C$$ all 3 steels are partly and / or entirely attacked, at 650$$^{circ}C$$ all of them show severe attack on the whole surface. 4.Specimens alloyed with Al by GESA perform well at all temperatures.

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 stagnant liquid Pb/Bi at elevated temperatures

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

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

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

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