Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON’, (II)

Hidaka, Masataka; SATO, Nobuhide; Ujita, Hiroshi

doi:10.1080/18811248.2002.9715230

Cited by 9 publications

(9 citation statements)

References 7 publications

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“…It implements a detailed and mechanistic analysis, solving the flow (mass, momentum and energy for multi-phase and multi-component) in three-dimensional or quasithree-dimensional configurations without overemployment of correlations (Cadiou et al, 2002;Maschek et al, 2005;Morita et al, 1999;Naitoh et al, 2005). The debris coolability analysis module was developed for the thermal hydraulics analysis of debris relocated in the lower head (Hidaka et al, 2002). The simulation results using this module showed good agreement with the experimental data for predicting of the flow spearhead location (Hidaka et al, 2002).…”

Section: Sampson Code Overviewmentioning

confidence: 70%

“…The debris coolability analysis module was developed for the thermal hydraulics analysis of debris relocated in the lower head (Hidaka et al, 2002). The simulation results using this module showed good agreement with the experimental data for predicting of the flow spearhead location (Hidaka et al, 2002). The containment vessel phenomena analysis module analyzes the behavior of pressure and temperature in a containment (Naitoh et al, 2005). vessel for a severe accident in a light water reactor based on the CONTAIN (Murata et al, 1997) code.…”

Section: Sampson Code Overviewmentioning

confidence: 94%

See 1 more Smart Citation

Passive depressurization accident management strategy for boiling water reactors

Liu

Erkan

Ishiwatari

et al. 2015

Nuclear Engineering and Design

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Section: Sampson Code Overviewmentioning

confidence: 70%

Section: Sampson Code Overviewmentioning

confidence: 94%

Passive depressurization accident management strategy for boiling water reactors

Liu

Erkan

Ishiwatari

et al. 2015

Nuclear Engineering and Design

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“…Several computer codes have been jointly developed to confirm the physical processes engaged in corium spreading: CORFLOW (Wittmaack 1997), CROCO (Michel et al 2000), LAVA (Allelein et al 2000), MELTSPREAD (Farmer et al 1990), RASPLAV (Bolshov et al 1995), SAMPSON (Hidaka et al 2002) and THEMA (Spindler & Veteau 2006). A scaling-based model has been developed by Dinh et al (2000).…”

Section: Existing Numerical Modelsmentioning

confidence: 99%

“…The mass, momentum and energy conservation are resolved for this 3D system, which allows the development of complex emplacement features related to solidification, such as lava lobes or tubes. The code LavaSIM (Hidaka et al 2002(Hidaka et al , 2005Proietti et al 2009), for example, has been successfully adapted to simulate lava-flow advance (see Fujita & Nagai, this volume, in press). …”

Section: Existing Numerical Modelsmentioning

confidence: 99%

Benchmarking lava-flow models

Cordonnier¹,

Lev

Garel

2015

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Prediction of the emplacement of volcanic mass flows (lava flows, pyroclastic density currents, debris avalanches and debris flows) is required for hazard and risk assessment, and for the planning of risk-mitigation measures. Numerical computer-based models now exist that are capable of approximating the motion of a given volume of volcanic material from its source to the deposition area. With these advances in technology, it is useful to compare the various codes in order to evaluate their respective suitability for real-time forecasting, risk preparedness and post-eruptive response. A 'benchmark' compares codes or methods, all aimed at simulating the same physical process using common initial and boundary conditions and outputs, but using different physical formulations, mathematical approaches and numerical techniques. We set up the basis for a future general benchmarking exercise on volcanic mass-flow models and, more specifically, establish a benchmark series for computational lava-flow modelling. We describe a set of benchmarks in this paper, and present a few sample results to demonstrate output analysis and code evaluation methodologies. The associated web-based communal facility for sharing test scenarios and results is also described.

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“…Numerical simulations of lava flows were proposed by Crisci et al (1986), Young and Wadge (1990) and Ishihara et al (1990). In the field of nuclear reactor severe-accident research, several computer codes have been developed to model corium spreading: CORFLOW (Wittmaack, 1997), CROCO (Michel et al, 2000), LAVA (Allelein et al, 2000), MELTSPREAD (Farmer et al, 1990), RASPLAV (Chudanov et al, 1994), SAMPSON (Hidaka et al, 2002), THEMA . In parallel a scaling-based model has been developed by Dinh et al (2000).…”

Section: Introductionmentioning

confidence: 98%