In the course of a small break LOCA in a Pressurized Water Reactor (PWR) the flow regime in the Reactor Cooling System (RCS) passes through a number of different phases and the filling level may decrease down to the point where the decay heat is transferred to the secondary side under Reflux-Condenser (RC) conditions. During RC, the steam formed in the core condensates in the Steam Generator (SG) U-tubes. For a limited range of break size and configuration, a continuous accumulation of condensate may cause the formation of boron-depleted slugs. If natural circulation reestablishes, as the RCS is refilled, boron-depleted slugs might be transported to the Reactor Pressure Vessel (RPV) and to the core. To draw conclusions on the risk of boron dilution processes in SB-LOCA transients, two important issues, the limitation of slug size and the onset of Natural Circulation (NC) have to be assessed on the basis of experimental data, as system Thermal-Hydraulic codes are limited in their capability to replicate the complex physical phenomena involved. The OECD PKL III tests were performed at AREVA’s PKL test facility in Erlangen, Germany, to evaluate important phases of the boron dilution transient in PWRs. Several integral and separate effect tests were conducted, addressing the inherent boron dilution issue. The PKL III integral transient test runs provide sufficient data to state major conclusions on the formation and maximum possible size of the boron-depleted slugs, their boron concentration and their transport into the RPV with the restart of NC. Some of these conclusions can be applied to reactor scale. It has to be mentioned, that even though this paper is based on PKL test results obtained within the OECD PKL project, the conclusions of this paper reflect the views of the authors and not necessarily of all the members of the OECD PKL project.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
PKL Tests on Heterogeneous Inherent Boron Dilution Following SB-LOCA: Applicability to Reactor Scale Available to Purchase
Klaus Umminger,
Klaus Umminger
AREVA-NP, Erlangen, Germany
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Simon Philipp Schollenberger,
Simon Philipp Schollenberger
AREVA-NP, Erlangen, Germany
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Se´bastien Cornille,
Se´bastien Cornille
AREVA-NP, La De´fense, France
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Claire Agnoux,
Claire Agnoux
EDF Septen, Villeurbanne, France
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Delphine Quintin,
Delphine Quintin
EDF Septen, Villeurbanne, France
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Philippe Freydier
Philippe Freydier
EDF Septen, Villeurbanne, France
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Klaus Umminger
AREVA-NP, Erlangen, Germany
Simon Philipp Schollenberger
AREVA-NP, Erlangen, Germany
Se´bastien Cornille
AREVA-NP, La De´fense, France
Claire Agnoux
EDF Septen, Villeurbanne, France
Delphine Quintin
EDF Septen, Villeurbanne, France
Philippe Freydier
EDF Septen, Villeurbanne, France
Paper No:
ICONE18-29400, pp. 433-439; 7 pages
Published Online:
April 8, 2011
Citation
Umminger, K, Schollenberger, SP, Cornille, S, Agnoux, C, Quintin, D, & Freydier, P. "PKL Tests on Heterogeneous Inherent Boron Dilution Following SB-LOCA: Applicability to Reactor Scale." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 433-439. ASME. https://doi.org/10.1115/ICONE18-29400
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