QUENCH is a series of experiments being performed at the Forschungszentrum Karlsruhe, to investigate quenching with water and cooling with steam of oxidized and partially degraded fuel rod bundle. Test QUENCH-07 was performed to address the effects of chemical behavior and degradation of B4C absorber rods, especially the oxidation of B4C, its interaction with stainless steel, formation and composition of gaseous reaction products and the impact of absorber rod degradation on surrounding rods. An unexpected feature of the experiment was the strong oxidation during the cooldown phase accompanied by an increased release of all gaseous species. Temperature escalation and hydrogen release during cooldown were observed for the first time in any steam cooled QUENCH experiment. Since not only the absorber rod was a novel feature but also the steam flow rate during cooldown was smaller in comparison with previous tests, it is not yet clear whether this escalation can be attributed to the effect of B4C.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3596-0
PROCEEDINGS PAPER
Results of the Quench-07 Experiment
Alexei Miassoedov,
Alexei Miassoedov
Forschungszentrum Karlsruhe, Karlsruhe, Germany
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Christoph Homann,
Christoph Homann
Forschungszentrum Karlsruhe, Karlsruhe, Germany
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Leo Sepold,
Leo Sepold
Forschungszentrum Karlsruhe, Karlsruhe, Germany
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Martin Steinbru¨ck
Martin Steinbru¨ck
Forschungszentrum Karlsruhe, Karlsruhe, Germany
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Alexei Miassoedov
Forschungszentrum Karlsruhe, Karlsruhe, Germany
Christoph Homann
Forschungszentrum Karlsruhe, Karlsruhe, Germany
Leo Sepold
Forschungszentrum Karlsruhe, Karlsruhe, Germany
Martin Steinbru¨ck
Forschungszentrum Karlsruhe, Karlsruhe, Germany
Paper No:
ICONE10-22137, pp. 123-129; 7 pages
Published Online:
March 4, 2009
Citation
Miassoedov, A, Homann, C, Sepold, L, & Steinbru¨ck, M. "Results of the Quench-07 Experiment." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 14–18, 2002. pp. 123-129. ASME. https://doi.org/10.1115/ICONE10-22137
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