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Hagen, S.; Sepold, L.; Wallenfels, K.P.; Hofmann, P.; Noack, V.; Schanz, G.; Schumacher, G.
Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 19941995
Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 19941995
AbstractAbstract
[en] The CORA quench experiments 12, 13 (PWR) and 17 (BWR) are in agreement with LOFT 2 and TMI: Flooding of hot Zircaloy clad fuel rods does not result in an immediate cooldown of the bundle, but produces remarkable temporary temperature increase, connected to a strong peak in hydrogen production. The PWR tests CORA 12 and CORA 13 are of the same geometrical arrangement and test conduct, with the exception of the shorter time between power shutdown and quench initiation for CORA 13. A higher temperature of the bundle at start of quenching was the consequence. BWR test CORA 17 - with B4C absorber and additional Zircaloy channel box walls - was in respect to the delay-time between power shutdown and start of quenching similar to test CORA 12. All tests showed during the quench phase the temporary temperature increase, correlated to a hydrogen peak. The CORA 17 test resulted immediately after quenching in a modest increase for 20 s and changed then in a steep increase, resulting in the highest temperature and hydrogen peaks of the three tests. CORA 17 also showed a temperature increase in the lower part of the bundle, in contrast to CORA 12 and CORA 13 with temperature increase only in the upper half of the bundle. We interpret this earlier starting and stronger reaction due to the influence of the boron carbide, the absorber material of the BWR test. B4C has an exothermic reaction rate 4 to 9 times larger than Zry and produces 5 to 6,6 times more hydrogen. Probably the hot remained columns of B4C (seen in the non-quench test CORA 16) react early in the quench process with the increased upcoming steam. The bundle temperature raised by this reaction increases the reaction rate (exponential dependency) of the remaining metallic Zry. Due to the larger amount of Zry in the BWR bundle (channel box walls) and the smaller steam input during the heatup phase (2 g/s instead of 6 g/s) more metallic Zry can have survived oxidation during the heatup phase. (orig./HP)
Original Title
Vergleich der Flutexperimente CORA-12, 13, 17 und der Einfluss des B4C auf das Flutverhalten von SWR-Buendeln
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Hueper, R. (ed.); Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung; 433 p; ISSN 0947-8620;
; Aug 1995; p. 262-288

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