Experimental Analyses by SIMMER-III on Molten Fuel Freezing and Boiling Pool Behavior

Yamano, Hidemasa; Tobita, Yoshiharu

doi:10.1299/jpes.3.249

Cited by 6 publications

(7 citation statements)

References 12 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Fundamental studies concerning numerical methods are performed to support the code development of COMPASS. The past results of the present project can be found in the references (Koshizuka et al, 2006(Koshizuka et al, , 2007(Koshizuka et al, , 2008a(Koshizuka et al, , 2008b(Koshizuka et al, , 2009a(Koshizuka et al, , 2009b(Koshizuka et al, , 2009cYamano and Tobita, 2009, 2010a, 2010bZhang et al, 2009Zhang et al, , 2010Yamamoto et al, 2008Yamamoto et al, , 2009Shirakawa et al, 2009;Uehara et al, 2009;Himi et al, 2008Himi et al, , 2009.…”

Section: Mps (Moving Particle Semi-implicit) Methods Was Developed To mentioning

confidence: 86%

“…In this paper, recent results of the COMPASS validation study for key phenomena in CDAs of SFRs are summarized, which include melt freezing and blockage formation, low-energy disruptive core motion, molten pool boiling, duct wall failure, and fuel pin failure and disruption. The selected experiments are GEYSER (Berthoud and Duret, 1989), THEFIS (Maschek et al, 1990), CABRI TPA2 (Yamano et al, 2009), SCARABEE BE+3 (Kayser and Stansfield, 1994) and CABRI E7 (Charpenel et al, 2000), respectively.…”

Section: Mps (Moving Particle Semi-implicit) Methods Was Developed To mentioning

confidence: 99%

See 1 more Smart Citation

Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code

Morita

Zhang

Koshizuka

et al. 2011

Nuclear Engineering and Design

Self Cite

View full text Add to dashboard Cite

A five-year research project has been initiated in 2005 to develop a code based on the MPS (Moving Particle Semi-implicit) method for detailed analysis of key phenomena in core disruptive accidents (CDAs) of sodium-cooled fast reactors (SFRs). The code is named COMPASS (Computer Code with Moving Particle Semi-implicit for Reactor Safety Analysis). The key phenomena include 1) fuel pin failure and disruption, 2) molten pool boiling, 3) melt freezing and blockage formation, 4) duct wall failure, 5) low-energy disruptive core motion, 6) debris-bed coolability, and 7) metal-fuel pin failure. Validation study of COMPASS is progressing for these key phenomena. In this paper, recent COMPASS results of detailed analyses for the several key phenomena are summarized. Simulations of GEYSER and THEFIS experiments were performed for dispersion 2 and freezing behaviors of molten materials in narrow flow channels. In particular, the latter experiment using melt-solid mixture is also related to fundamental behavior of low energy disruptive core. CABRI-TPA2 experiment was simulated for boiling behavior of molten core pool. Expected mechanism of heat transfer between molten fuel and steel mixture was reproduced by the simulation. Analyses of structural dynamics using elastoplastic mechanics and fracture criteria were performed for SCARABEE BE+3 and CABRI E7 experiments. These two analyses are especially focused on thermal and mechanical failure of steel duct wall and fuel pin, respectively. The present results demonstrate COMPASS will be useful to understand and clarify the key phenomena of CDAs in SFRs in details.

show abstract

Section: Mps (Moving Particle Semi-implicit) Methods Was Developed To mentioning

confidence: 86%

Section: Mps (Moving Particle Semi-implicit) Methods Was Developed To mentioning

confidence: 99%

Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code

Morita

Zhang

Koshizuka

et al. 2011

Nuclear Engineering and Design

Self Cite

View full text Add to dashboard Cite

show abstract

“…From these viewpoints, this study selected the CABRI-EFM1 experiment, which realized fuel melting after sodium voiding, for the thermal failure mode. (17) This experiment has already been calculated by SIMMER-III, focusing on fuel freezing and blockage behavior (18) , whereas the fuel disruption behavior is emphasized in this study. Of many experiments in the CABRI programs, pure TOP experiments, E5 and E7, were the mechanical failure mode using a large-diameter annular fuel pellet.…”

Section: Fuel-pin Disruption Behaviormentioning

confidence: 90%

“…(25) Figure 3 compares the initial fuel temperature profiles between the SAS4A result, the SIMMER-III detailed pin model, and simple model. The simple pin model, which was used in the previous calculation (18) , calculates fuel temperatures represented only by two radial nodes (interior and outer surface). Although the surface node size is so thin as to obtain good thermal response, the thermal conduction is not well calculated in the interior node.…”

Section: Cabri-efm1 Experimentsmentioning

confidence: 99%

Experimental Analyses by SIMMER-III on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion

Yamano

Tobita

2010

JPES

Self Cite

View full text Add to dashboard Cite

This paper describes experimental analyses using the SIMMER-III computer code, which is a two-dimensional multi-component multi-phase Eulerian fluid-dynamics code. Two topics of key phenomena in core disruptive accidents were presented in this paper: fuel-pin disruption, and low energy disrupted core motion. Related experimental database were reviewed to select appropriate experiments. To analyze the fuel-pin disruption behavior, the CABRI-EFM1 and the CABRI-E7 in-pile experiments were selected. The SIMMER-III calculation was in good agreement with the overall fuel-pin disruption and dispersion behavior, which was characterized by a thermal pin-failure mode, observed in the CABRI-EFM1 experiment. Since the code framework of SIMMER-III cannot treat a mechanical deformation and breakup behavior, the SAS4A code was applied to the CABRI-E7 experiment, where a mechanical pin-failure mode was realized. In this study, such a failure mode was also reasonably simulated. The low-energy disrupted core consists principally of fuel particles and liquid steel (or fuel). Under such a mixture condition, significantly reduced melt penetration length was obtained in the THEFIS out-of-pile experiments. SIMMER-III well simulated the melt freezing and blockage behavior observed in the experiment.

show abstract

“…The comprehensive code assessment study previously mentioned emphasized on the transient multi-phase flow in the transition phase of CDAs within the limitation of the two-dimensional code. Extensive code validation study was also devoted to similar transient multi-phase flows (Yamano and Tobita, 2009, 2010. Unlike these code validation studies, the present study focused on a series of phenomena from the duct wall failure to the fuel relocation.…”

mentioning

confidence: 99%

Experimental analyses by SIMMER-III on duct-wall failure and fuel discharge/relocation behavior

Yamano

Tobita

2014

Mechanical Engineering Journal

Self Cite

View full text Add to dashboard Cite

This paper describes experimental analyses using SIMMER-III and-IV, which are respectively two-and three-dimensional multi-component multi-phase Eulerian fluid-dynamics codes, for the purpose of integral code validation. Two topics of key phenomena in core disruptive accidents of sodium-cooled fast reactors are presented in this paper: duct-wall failure and fuel discharge/relocation behavior. To analyze the duct-wall failure behavior, the SCARABEE BE+3 in-pile experiments were selected. The SIMMER-III calculation was in good agreement with the overall event progression; which was characterized by coolant boiling, clad melting, fuel failure, molten pool formation, duct-wall failure, etc.; observed in the experiment. The CAMEL C6 experiment investigated the fuel discharge and relocation behavior through a simulated control rod guide tube, which is important in evaluating the neutronic reactivity. SIMMER-IV well simulated fuel-coolant interaction, sodium voiding, fuel relocation behavior observed in the experiment. These experimental analyses indicated the validity of the SIMMER-III and-IV computer code for the duct wall failure and fuel discharge/relocation behavior. : Sodium-cooled fast reactor, Core disruptive accident, Multi-phase flow, Simulation code, SIMMER-III, Wall failure, Fuel discharge, Fuel relocation 1. Introduction The SIMMER-III computer code has been developed and used to analyze the event progression of core disruptive accidents (CDAs) in sodium-cooled fast reactors (SFRs) in Japan Atomic Energy Agency (JAEA) (Tobita, et al., 1999). SIMMER-III is a two-dimensional multi-component multi-phase Eulerian fluid-dynamics code, coupled with fuel pin model and space-dependent neutronics model (Yamano, et al., 2003). This computer code has to simulate complex phenomena in CDAs, such as sodium voiding, fuel and clad melting, duct wall failure, molten core material discharge and relocation, and so on. A comprehensive and systematic assessment (verification and validation) program of the SIMMER-III code has been conducted for fundamental assessment of individual code models (Kondo, et al., 1997) and for integral code assessment (Kondo, et al., 1999). Areas of interests in the latter assessment problems were boiling pool dynamics, fuel relocation and freezing (Kamiyama, et al., 2006), fuel-coolant interaction (FCI) (Morita, et al., 1999), core expansion dynamics and disrupted core neutronics. Especially through sodium experimental calculations, it was demonstrated that SIMMER-III was well validated for simulating transient multi-phase flow phenomena occurring during CDAs (Tobita, et al., 2006). In parallel with the code assessment efforts, a three-dimensional SIMMER-IV code was developed with retaining exactly the same framework in physical models as SIMMER-III (Yamano, et al., 2008). Fuel relocation is very important in the CDA event progression because fuel discharge from the core can significantly mitigate the neutronic reactivity. In particular, effective is fuel discharge through a large-diameter duct, suc...

show abstract

Experimental Analyses by SIMMER-III on Molten Fuel Freezing and Boiling Pool Behavior

Cited by 6 publications

References 12 publications

Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code

Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code

Experimental Analyses by SIMMER-III on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion

Experimental analyses by SIMMER-III on duct-wall failure and fuel discharge/relocation behavior

Contact Info

Product

Resources

About