18th International Conference on Nuclear Engineering: Volume 4, Parts a and B 2010
DOI: 10.1115/icone18-29400
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PKL Tests on Heterogeneous Inherent Boron Dilution Following SB-LOCA: Applicability to Reactor Scale

Abstract: 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… Show more

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“…Plenty of institutions have contributed a lot on the Design Basis Condition transients with different simulation tools such as ATHLET, RETRAN, TRAC, CATHARE, RELAP5, and TRACE for di?erent reactor types for the variations of reactor thermal hydraulic parameters. A large amount of knowledge about thermohydraulic processes in the reactor cooling systems under different operational statuses and accident conditions has been gained based on a vast number of experimental and analytical studies (Aksan, 2008;Umminger et al, 2010;Kozmenkov and Rohde, 2013;Asmolov et al, 2014;Wang et al, 2015;Bestion, 2017). The recent studies focus more on the performance of passive safety systems and the increased safety margins of newly developed reactors, as well as the code to code comparisons (Nevo et al, 2012;Wang et al, 2012;Hu et al, 2013Hu et al, , 2014Salehi and Jahanfarnia, 2016;Yousif et al, 2017).…”
Section: Simulation Tools Used For Hpr1000mentioning
confidence: 99%
“…Plenty of institutions have contributed a lot on the Design Basis Condition transients with different simulation tools such as ATHLET, RETRAN, TRAC, CATHARE, RELAP5, and TRACE for di?erent reactor types for the variations of reactor thermal hydraulic parameters. A large amount of knowledge about thermohydraulic processes in the reactor cooling systems under different operational statuses and accident conditions has been gained based on a vast number of experimental and analytical studies (Aksan, 2008;Umminger et al, 2010;Kozmenkov and Rohde, 2013;Asmolov et al, 2014;Wang et al, 2015;Bestion, 2017). The recent studies focus more on the performance of passive safety systems and the increased safety margins of newly developed reactors, as well as the code to code comparisons (Nevo et al, 2012;Wang et al, 2012;Hu et al, 2013Hu et al, , 2014Salehi and Jahanfarnia, 2016;Yousif et al, 2017).…”
Section: Simulation Tools Used For Hpr1000mentioning
confidence: 99%
“…The OECD PKL tests on boron dilution greatly improved the knowledge of the transient and of the complex physical phenomena involved. With these PKL tests and the derived findings as a substantial element, the final assessment against boron dilution for specific plant designs is finally to be done in conjunction with thermohydraulic system codes (system behavior), investigations on mixing in the RPV downcomer and lower plenum (CFD or mixing experiments) and neutronics analysis (consequences on core) [9].…”
Section: Boron Dilution Following Sb-locamentioning
confidence: 99%