The QUENCH-14 experiment investigated the effect of M5® cladding material on bundle oxidation and core reflood, in comparison with tests QUENCH-06 (ISP-45) that used standard Zircaloy-4 and QUENCH-12 that used VVER E110-claddings. The PWR bundle configuration of QUENCH-14 with a single unheated rod, 20 heated rods, and four corner rods was otherwise identical to QUENCH-06. The test was conducted in principle with the same protocol as QUENCH-06, so that the effects of the change of cladding material could be observed more easily. Pre-test calculations were performed by the Paul Scherrer Institute (Switzerland) using SCDAPSIM, SCDAP/RELAP5 and MELCOR codes. The experiment started with a pre-oxidation phase in steam, lasting 3100 s at 1500 K peak bundle temperature. After a further temperature increase to maximal bundle temperature of 2050 K the bundle was flooded with 41 g/s water from the bottom. The peak temperature of ∼2300 K was measured on the bundle shroud, shortly after quench initiation. The electrical power was reduced to 3.9 kW during the reflood phase to simulate effective decay heat levels. The complete bundle cooling was reached in 300 s after reflood initiation. The development of the oxide layer growth during the test was rather defined by measurements performed on the three Zircaloy-4 corner rods withdrawn successively from the bundle. The withdrawal of Zircaloy-4 and E110 corner rods after the test allowed a comparison of the different alloys in one test. One heated rod with M5 cladding was withdrawn after the test for a detailed analysis of oxidation degree and measurement of absorbed hydrogen. Post-test examinations showed neither breakaway cladding oxidation nor noticeable melt relocation between rods. Different from the QUENCH-14 (M5) findings, the QUENCH-12 test with the E110 claddings performed under similar conditions had resulted in intensive breakaway effect at cladding and shroud surfaces during the pre-oxidation phase and local melt relocation on reflood initiation. The hydrogen production in QUENCH-14 up to reflood was similar to QUENCH-06 and QUENCH-12 bundle tests. During reflood 5 g hydrogen were released which is similar to QUENCH-06 (4 g) but much less than during quench phase of QUENCH-12 (24 g). The reason for the different behaviour of the Zr1%Nb cladding alloys is the different oxide scale properties of both materials.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Experimental Results of Reflood Bundle Test QUENCH-14 With M5® Cladding Tubes
Juri Stuckert,
Juri Stuckert
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Mirco Große,
Mirco Große
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Leo Sepold,
Leo Sepold
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Martin Steinbru¨ck
Martin Steinbru¨ck
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Juri Stuckert
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Mirco Große
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Leo Sepold
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Martin Steinbru¨ck
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Paper No:
ICONE17-75266, pp. 455-461; 7 pages
Published Online:
February 25, 2010
Citation
Stuckert, J, Große, M, Sepold, L, & Steinbru¨ck, M. "Experimental Results of Reflood Bundle Test QUENCH-14 With M5® Cladding Tubes." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 455-461. ASME. https://doi.org/10.1115/ICONE17-75266
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