Search Results - "Steinbrück, M."

Air oxidation of Zircaloy-4, M5® and ZIRLO™ cladding alloys at high temperatures by Steinbrück, M., Böttcher, M.

“…The paper presents the results of isothermal and transient oxidation experiments of the advanced cladding alloys M5® and ZIRLO™ in comparison to Zircaloy-4 in…”
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Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure by Kashkarov, E.B., Sidelev, D.V., Syrtanov, M.S., Tang, C., Steinbrück, M.

“…•Zr-1Nb alloy coated by dense Cr exhibits better oxidation performance.•Transition time into non-protective behavior increases with coating…”
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High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage by Steinbrück, M., Stegmaier, U., Große, M., Czerniak, L., Lahoda, E., Daum, R., Yueh, K.

“…•Single-rod oxidation tests in steam with commercially produced Cr coated Optimized ZIRLO cladding segments were carried out up to very high temperatures of…”
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Degradation and oxidation of B4C control rod segments at high temperatures by STEINBRÜCK, M

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Synopsis and outcome of the QUENCH experimental program by Steinbrück, M., Große, M., Sepold, L., Stuckert, J.

“…The paper gives an overview of the main outcome of the QUENCH program launched in 1997 at the Karlsruhe Institute of Technology (KIT), formerly Karlsruhe…”
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In-situ neutron radiography investigations of the reaction of Zircaloy-4 in steam, nitrogen/steam and air/steam atmospheres by Grosse, M., Pulvermacher, S., Steinbrück, M., Schillinger, B.

“…In the framework of nuclear safety research the high temperature reaction behavior of the classical pressurized water reactor cladding material Zircaloy-4 in…”
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Hafnium oxidation at high temperature in steam by Guilbert-Banti, S., Viretto, A., Barrachin, M., Tanguy, C., Steinbrück, M., Stuckert, J.

“…To assess the potential impact of using hafnium as absorber material in LWRs in high temperature accidental situations, the oxidation behavior of hafnium was…”
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Experiments on silver-indium-cadmium control rod failure during severe nuclear accidents by Steinbrück, M., Stegmaier, U., Grosse, M.

“…•Ag-In-Cd control rod failure occurred at temperatures between 1470 and 1600K.•Inner oxidation of the zircaloy guide tube retards control rod failure.•After…”
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Separate-effect tests on zirconium cladding degradation in air ingress situations by Duriez, C., Steinbrück, M., Ohai, D., Meleg, T., Birchley, J., Haste, T.

“…In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel rods will be exposed to air-containing atmospheres at high…”
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Investigation of the 3D hydrogen distribution in zirconium alloys by means of neutron tomography by Grosse, M., Schillinger, B., Trtik, P., Kardjilov, N., Steinbrück, M.

“…The fuel rod claddings in nuclear light water reactors are made of zirconium alloys. Corrosion of these alloys during operation and in particular high…”
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Cladding oxidation during air ingress. Part I: Experiments on air ingress by Stuckert, J., Hózer, Z., Kiselev, A., Steinbrück, M.

“…•Summary of recent experiments on air ingress.•Reaction of nitrogen with α-Zr(O) under oxygen starvation conditions.•Formation of very porous and fragile…”
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A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments by Haste, T., Steinbrück, M., Barrachin, M., de Luze, O., Grosse, M., Stuckert, J.

“…•The results of the experiments CORA, QUENCH and Phébus SFD/FP are summarised.•All phenomena expected up to melt movement to the lower head are shown…”
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QUENCH-LOCA program at KIT on secondary hydriding and results of the commissioning bundle test QUENCH-L0 by Stuckert, J., Große, M., Rössger, C., Klimenkov, M., Steinbrück, M., Walter, M.

“…► Cladding bursts took place during heating at temperatures between 1123 and 1223K. ► Around oxide area at inner cladding surface hydrogen-containing bands…”
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Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool by Coindreau, O., Jäckel, B., Rocchi, F., Alcaro, F., Angelova, D., Bandini, G., Barnak, M., Behler, M., Da Cruz, D.F., Dagan, R., Drai, P., Ederli, S., Herranz, L.E., Hollands, T., Horvath, G., Kaliatka, A., Kljenak, I., Kotsuba, O., Lind, T., López, C., Mancheva, K., Matejovic, P., Matkovič, M., Steinbrück, M., Stempniewicz, M., Thomas, R., Vileiniskis, V., Visser, D.C., Vokáč, P., Vorobyov, Y., Zhabin, O.

“…•Benchmark of 6 SA codes (14 participants) for two accident scenarios in a Spent Fuel Pool.•Differences in draining velocity induced scattering in the onset of…”
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Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO™ cladding tubes in comparison with results of previous QUENCH tests by Stuckert, J., Birchley, J., Große, M., Jaeckel, B., Steinbrück, M.

“…► Neither breakaway effect nor melt relocation was observed during a test with the ZIRLO™ bundle flooded at 2100 K. ► A noticeable factor of cladding oxidation…”
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Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type by Sepold, L., Hering, W., Schanz, G., Scholtyssek, W., Steinbrück, M., Stuckert, J.

“…The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate core degradation and the hydrogen source term that results…”
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Recent advances in understanding ruthenium behaviour under air-ingress conditions during a PWR severe accident by Giordano, P., Auvinen, A., Brillant, G., Colombani, J., Davidovich, N., Dickson, R., Haste, T., Kärkelä, T., Lamy, J.S., Mun, C., Ohai, D., Pontillon, Y., Steinbrück, M., Vér, N.

“…In a hypothetical severe accident in a Pressurised Water Reactor (PWR), Fission Products (FPs) can be released from the overheated nuclear fuel and partially…”
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Experimental results of the QUENCH-16 bundle test on air ingress by Stuckert, J., Steinbrück, M.

“…The out-of-pile bundle experiment QUENCH-16 on air ingress was conducted in the electrically heated 21-rod QUENCH facility at KIT in July 2011. It was…”
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Tantalum Oxidation in Steam Atmosphere by Angelici Avincola, V., Janek, M., Stegmaier, U., Steinbrück, M., Seifert, H. J.

“…The oxidation behavior of tantalum in steam was investigated in the temperature range of 600–1100 °C. Thermogravimetric measurements were used to determine the…”
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Core loss during a severe accident (COLOSS) by Adroguer, B, Chatelard, P, Van Dorsselaere, J.P, Duriez, C, Cocuaud, N, Bellenfant, L, Bottomley, D, Vrtilkova, V, Mueller, K, Hering, W, Homann, C, Krauss, W, Miassoedov, A, Steinbrück, M, Stuckert, J, Hozer, Z, Bandini, G, Birchley, J, Berlepsch, T.v, Buck, M, Benitez, J.A.F, Virtanen, E, Marguet, S, Azarian, G, Plank, H, Veshchunov, M, Zvonarev, Y, Goryachev, A

“…The core loss during a severe accident (COLOSS) project is a 3-year shared-cost action which started in February 2000. The project is concerned with the…”
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