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Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters

Authors: Liancheng, Guo; Rineiski Andrei;

Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters

Abstract

To avoid settling of molten materials directly on the vessel wall in severe accident sequences, the implementation of a ‘core catcher’ device in the lower plenum of sodium fast reactor designs is considered. The device is to collect, retain and cool the debris, created when the corium falls down and accumulates in the core catcher, while interacting with surrounding coolant. This Fuel-Coolant Interaction (FCI) leads to a potentially energetic heat and mass transfer process which may threaten the vessel integrity. For simulations of severe accidents, including FCI, the SIMMER code family is employed at KIT. SIMMER-III and SIMMER-IV are advanced tools for the core disruptive accidents (CDA) analysis of liquid-metal fast reactors (LMFRs) and other GEN-IV systems. They are 2D/3D multi-velocity-field, multiphase, multicomponent, Eulerian, fluid dynamics codes coupled with a fuel-pin model and a space- and energy-dependent neutron kinetics model. However, the experience of SIMMER application to simulation of corium relocation and related FCI is limited. It should be mentioned that the SIMMER code was not firstly developed for the FCI simulation. However, the related models show its basic capability in such complicate multiphase phenomena. The objective of the study was to preliminarily apply this code in a large-scale simulation. An in-vessel model based on European Sodium Fast Reactor (ESFR) was established and calculated by the SIMMER code. In addition, a sensitivity analysis on some modeling parameters is also conducted to examine their impacts. The characteristics of the debris in the core catcher region, such as debris mass and composition are compared. Besides that, the pressure history in this region, the mass of generated sodium vapor and average temperature of liquid sodium, which can be considered as FCI quantitative parameters, are also discussed. It is expected that the present study can provide some numerical experience of the SIMMER code in plant-scale corium relocation and related FCI simulation.

Subjects by Vocabulary

Microsoft Academic Graph classification: Materials science Nuclear engineering Mass transfer Fluid dynamics Sensitivity (control systems) Corium Core catcher Coolant

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(2) Moriyama, Kiyofumi, Takagi Seiji, Muramatsu Ken, Nakamura Hideo and Maruyama Yu, “Evaluation of containment failure probability by Ex-vessel steam explosion in Japanese LWR plants”, Journal of Nuclear Science and Technology, Vol. 43, No. 7 (2006): pp. 774-784.

(3) Meignen Renaud, Picchi Stephane, Lamome Julien, Raverdy Bruno, Escobar, Sebastian Castrillon and Nicaise Gregory, “The challenge of modeling fuel-coolant interaction: Part I - Premixing”, Nuclear Engineering and Design, Vol.

(4) Yamano Hidemasa, et al., “SIMMER-III: A computer program for LMFR core disruptive accident analysis”. JNC TN9400 2003-071 Report, August 2003.

(5) Morita Koji, Matsumoto Tatsuya, Akasaka Ryo, Fukuda Kenji, Suzuki Tohru, Tobita Yoshihara, Yamano Hidemasa and Kondo Satoru, “Development of multicomponent vaporization / condensation model for a reactor safety analysis code SIMMER-III Theoretical modeling and basic verification,” Nuclear Engineering and Design, Vol. 220 (2003): pp. 224- 239.

(6) Morita, Koji, Kondo Satoru, Tobita Yoshihara and Brear David J., “SIMMER-III applications to fuel-coolant interactions”, Nuclear Engineering and Design, Vol. 189 (1999): pp. 337-357.

(7) Fiorini Gian Luigi, Vasile Alfredo, “European Commission - 7th Framework Programme The Collaborative Project on European Sodium Fast Reactor (CP-ESFR)”, Nuclear Engineering and Design 241 (2011) 3461- 3469.

(8) Mikityuk Konstantin et al., ESFR-SMART: new Horizon2020 project on SFR safety, Proc. Int. Conf.on Fast Reactors and Related Fuel Cycles (FR17), Yekaterinburg, Russia, June 26-29, 2017.

(9) Bachrata Andrea., Bertrand F., and Lemasson D., “Unprotected Loss of Flow simulation on ASTRID CFV-V3 reactor core”, Proceedings of ICAPP, Nice France, May 03-06, 2015.

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    Average
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citations
This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Citations provided by BIP!
popularity
This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.
BIP!Popularity provided by BIP!
influence
This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Influence provided by BIP!
impulse
This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.
BIP!Impulse provided by BIP!
1
Average
Average
Average
Green