Behavior of the corium pool in the lower head is still a critical issue in understanding of PWR core meltdown accidents. One of the key parameter for assessing the vessel mechanical strength is the resulting heat flux at the pool-vessel interface. A number of studies [1]–[3] have already been performed to pursue the understanding of a severe accident with core melting, its course, major critical phases and timing and the influence of these processes on the accident progression. Uncertainties in modeling these phenomena and in the application to reactor scale will undoubtedly persist. These include e.g. formation and growth of the in-core melt pool, relocation of molten material after the failure of the surrounding crust, characteristics of corium arrival in residual water in the lower head, corium stratifications in the lower head after the debris re-melting [4]. These phenomena have a strong impact on a potential termination of a severe accident. The main objective of the LIVE program [5] at FZK is to study the core melt phenomena both experimentally in large-scale 3D geometry and in supporting separate-effects tests, and analytically using CFD codes in order to provide a reasonable estimate of the remaining uncertainty band under the aspect of safety assessment. Within the LIVE experimental program several tests have been performed with water and with non-eutectic melts (mixture of KNO3 and NaNO3) as simulant fluids. The results of these experiments, performed in nearly adiabatic and in isothermal conditions, allow a direct comparison with findings obtained earlier in other experimental programs (SIMECO, ACOPO, BALI, etc.) and will be used for the assessment of the correlations derived for the molten pool behavior. The information obtained from the LIVE experiments includes heat flux distribution through the reactor pressure vessel wall in transient and steady state conditions, crust growth velocity and dependence of the crust formation on the heat flux distribution through the vessel wall. Supporting post-test analysis contributes to characterization of solidification processes of binary non-eutectic melts. Complimentary to other international programs with real corium melts, the results of the LIVE activities provide data for a better understanding of in-core corium pool behavior. The experimental results are being used for development of mechanistic models to describe the in-core molten pool behavior and their implementation in the severe accident codes like ASTEC. The paper summarizes the objectives of the LIVE program and presents the main results obtained in the LIVE experiments up to now.
Skip Nav Destination
16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4817-5
PROCEEDINGS PAPER
LIVE Experiments on Melt Behavior in the RPV Lower Head
Alexei Miassoedov,
Alexei Miassoedov
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Search for other works by this author on:
Thomas Cron,
Thomas Cron
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Search for other works by this author on:
Jerzy Foit,
Jerzy Foit
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Search for other works by this author on:
Xiaoyang Gaus-Liu,
Xiaoyang Gaus-Liu
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Search for other works by this author on:
Silke Schmidt-Stiefel,
Silke Schmidt-Stiefel
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Search for other works by this author on:
Thomas Wenz
Thomas Wenz
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Search for other works by this author on:
Alexei Miassoedov
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Thomas Cron
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Jerzy Foit
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Xiaoyang Gaus-Liu
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Silke Schmidt-Stiefel
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Thomas Wenz
Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany
Paper No:
ICONE16-48650, pp. 739-746; 8 pages
Published Online:
June 24, 2009
Citation
Miassoedov, A, Cron, T, Foit, J, Gaus-Liu, X, Schmidt-Stiefel, S, & Wenz, T. "LIVE Experiments on Melt Behavior in the RPV Lower Head." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance. Orlando, Florida, USA. May 11–15, 2008. pp. 739-746. ASME. https://doi.org/10.1115/ICONE16-48650
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
CFD Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Influence of Turbulence Model and Mesh Refinement on the Vessel Thermal Loading During PTS Transient
J. Pressure Vessel Technol (June,2011)
COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
ASME J of Nuclear Rad Sci (July,2016)
Core Melt Solidification Characteristics in PRV Lower Head-Experimental Results From LIVE Tests
J. Eng. Gas Turbines Power (October,2010)
Related Chapters
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Czech and Slovakian Codes
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition