Properties of Light Water Reactor Core Melts

Nazaré, Shonali; Ondracek, G.; Schulz, B.

doi:10.13182/nt77-a31748

Cited by 18 publications

(16 citation statements)

References 7 publications

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“…The MCCI conservation of mass equations and thermo-physical property subroutines consider most core and concrete metals and their corresponding oxides, so that a wide range of cases can be considered. Melt viscosity is calculated using the Andrade formula (see Nazare et al [42]) with a correction for SiO 2 as developed by Shaw [43]. Viscosity enhancement due to buildup of solids within the melt can be calculated using either the Ishii-Zuber [24] or Kunitz [44] models.…”

Section: Fig 3 Core Oxide and Steel Solid-fraction Functions Assumementioning

confidence: 99%

Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction Analyses with MELTSPREAD & CORQUENCH

Robb¹,

Farmer²,

Francis³

2013

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Section: Fig 3 Core Oxide and Steel Solid-fraction Functions Assumementioning

confidence: 99%

Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction Analyses with MELTSPREAD & CORQUENCH

Robb¹,

Farmer²,

Francis³

2013

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“…The conservation of mass equations and thermophysical property subroutines consider most core and concrete metals and their corresponding oxides, so that a wide range of cases can be considered. Melt viscosity is calculated using the Andrade formula (see Nazare et al 44 ) with a correction for SiO 2 as developed by Shaw. 45 Viscosity enhancement due to buildup of solids within the melt is calculated using the Ishii-Zuber model.…”

Section: Methodsmentioning

confidence: 99%

OECD MCCI project final report, February 28, 2006.

Farmer¹,

Lomperski²,

Kilsdonk³

et al. 2011

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“…The solidus and liquidus temperatures are required to be distinct, and the solid fraction in each phase is assumed to vary linearly between the solidus and liquidus values. The oxide and metal liquid phase viscosities are evaluated using the Da Andrade formula [89] at a melting temperature corresponding to the solidus for each phase. For the metal liquid phase, the viscosity is evaluated through the equation,…”

Section: Plotting File Output Descriptionsmentioning

confidence: 99%

“…These factors are initialized in subroutine CPROPI. In subroutine VISCF, the actual oxide liquid phase viscosity, ( ), is set equal to the larger of the two viscosities predicted by the De Andrade [89] and Shaw viscosity [96] models (i.e., Eqs. B-41 and B-46, respectively).…”

Section: Plotting File Output Descriptionsmentioning

confidence: 99%

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The MELTSPREAD Code for Modeling of Ex-Vessel Core Debris Spreading Behavior, Code Manual – Version3-beta

Farmer

2017

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MELTSPREAD3 is a transient one-dimensional computer code that has been developed to predict the gravity-driven flow and freezing behavior of molten reactor core materials (corium) in containment geometries. Predictions can be made for corium flowing across surfaces under either dry or wet cavity conditions. The spreading surfaces that can be selected are steel, concrete, a user-specified material (e.g., a ceramic), or an arbitrary combination thereof. The corium can have a wide range of compositions of reactor core materials that includes distinct oxide phases (predominantly 2 , 2 , and steel oxides) plus metallic phases (predominantly Zr and steel). The code requires input that describes the containment geometry, melt "pour" conditions, and cavity atmospheric conditions (i.e., pressure, temperature, and cavity flooding information). For cases in which the cavity contains a preexisting water layer at the time of RPV failure, melt jet breakup and particle bed formation can be calculated mechanistically given the time-dependent melt pour conditions (input data) as well as the heatup and boiloff of water in the melt impingement zone (calculated). For core debris impacting either the containment floor or previously spread material, the code calculates the transient hydrodynamics and heat transfer which determine the spreading and freezing behavior of the melt. The code predicts conditions at the end of the spreading stage, including melt relocation distance, depth and material composition profiles, substrate ablation profile, and wall heatup. Code output can be used as input to other models such as CORQUENCH that evaluate long term core-concrete interaction behavior following the transient spreading stage.MELTSPREAD3 was originally developed to investigate BWR Mark I liner vulnerability, but has been substantially upgraded and applied to other reactor designs (e.g., the EPR), and more recently to the plant accidents at Fukushima Daiichi. The most recent round of improvements that are documented in this report have been specifically implemented to support industry in developing Severe Accident Water Management (SAWM) strategies for Boiling Water Reactors. This document is a Code Manual which contains i) a technology review, ii) descriptions of models and correlations, iii) descriptions of the implicit, finite difference numerical solution scheme, iv) a user's guide, and v) a summary of code validation calculations that have been performed to date.

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Properties of Light Water Reactor Core Melts

Cited by 18 publications

References 7 publications

Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction Analyses with MELTSPREAD & CORQUENCH

Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction Analyses with MELTSPREAD & CORQUENCH

OECD MCCI project final report, February 28, 2006.

The MELTSPREAD Code for Modeling of Ex-Vessel Core Debris Spreading Behavior, Code Manual – Version3-beta

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