The QUENCH experimental programme at Forschungszentrum Karlsruhe (FZK) investigates phenomena associated with reflood of a degrading core under postulated severe accident conditions, but where the geometry is still mainly rod-like and degradation is still at an early phase. The QUENCH test bundle is electrically heated and consists of 21 fuel rod simulators with a total length of approximately 2.5 m. The cladding and grid spacers are identical to those used in Pressurized Water Reactors (PWR) whereas the fuel is represented by ZrO2 pellets. Experiment QUENCH-14 was successfully performed at FZK in July 2008 and is the first in this programme where Zr-Nb alloy M5® is used as the fuel rod simulator cladding. QUENCH-14 was otherwise essentially the same as experiment QUENCH-06, which was the subject of the CSNI ISP-45 exercise. It is also the first of three experiments in the QUENCH-ACM series, recently launched to examine the effect of advanced cladding materials on oxidation and quenching under otherwise similar conditions. Pre- and post-test analyses were performed at PSI using a local version of SCDAP/RELAP5 and MELCOR 1.8.6, using input models which had already been benchmarked against QUENCH-06 data. Preliminary pre-test calculations with both codes and alternative correlations for the oxidation kinetics indicated that the planned test protocol would achieve the desired objective of exhibiting whatever effects might arise from the change in cladding-material in the course of a transient similar to QUENCH-06. Several correlations were implemented in the models, namely Cathcart-Pawel, Urbanic-Heidrick, Leistikow-Schanz and Prater-Courtright for Zircaloy-4 (Zry-4), and additionally a new candidate correlation for M5® based on recent separate-effects tests performed at FZK on M5® cladding samples. Analyses of the QUENCH-14 data demonstrate strengths and limitations of the various models. Some tentative recommendations are made concerning choice of correlation and effect of cladding material.
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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
Analysis of the Quench-14 Bundle Test With M5® Cladding
Jonathan C. Birchley,
Jonathan C. Birchley
Paul Scherrer Institut, Villigen, Switzerland
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Bernd Jaeckel,
Bernd Jaeckel
Paul Scherrer Institut, Villigen, Switzerland
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Timothy J. Haste,
Timothy J. Haste
Paul Scherrer Institut, Villigen, Switzerland
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Martin Steinbrueck,
Martin Steinbrueck
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
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Juri Stuckert
Juri Stuckert
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
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Jonathan C. Birchley
Paul Scherrer Institut, Villigen, Switzerland
Bernd Jaeckel
Paul Scherrer Institut, Villigen, Switzerland
Timothy J. Haste
Paul Scherrer Institut, Villigen, Switzerland
Martin Steinbrueck
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Juri Stuckert
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Paper No:
ICONE17-75099, pp. 341-348; 8 pages
Published Online:
February 25, 2010
Citation
Birchley, JC, Jaeckel, B, Haste, TJ, Steinbrueck, M, & Stuckert, J. "Analysis of the Quench-14 Bundle Test With M5® Cladding." 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. 341-348. ASME. https://doi.org/10.1115/ICONE17-75099
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