Natural convection heat transfer in corium pools: A review work of experimental studies

Zhang, Luteng; Zhou, Yukun; Zhang, Yapei; Tian, Wenxi; Qiu, Suizheng; Su, G.H.

doi:10.1016/j.pnucene.2014.11.021

Cited by 67 publications

(9 citation statements)

References 45 publications

(79 reference statements)

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“…Figure 7 shows a contour plot of the predicted temperature in a cross-section at the midpoint of the main shell, viewing down the axis of the calandria. The temperature field resembled those observed in experiments with LWR geometries [2], with an upper, nearly isothermal region, and a lower, stratified region, both surrounded by a thin boundary layer. A side view of half of the flow field at the mid-plane of the model is shown in Figure 8.…”

Section: Calandria Modelsupporting

confidence: 71%

“…The crust thickness then adjusts to accommodate the heat flow and the outside conditions. Natural convection in corium pools is the subject of past and ongoing research in the light-water reactor (LWR) community [2]. Figure 1 shows side and front views of a corium pool in a CANDU calandria (see Figure 6 for a perspective view of the pool only).…”

Section: Introductionmentioning

confidence: 99%

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Computational Fluid Dynamics Study of a Corium Pool in a Candu Calandria

David¹

2017

CNL Nuclear Review

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Section: Calandria Modelsupporting

confidence: 71%

Section: Introductionmentioning

confidence: 99%

Computational Fluid Dynamics Study of a Corium Pool in a Candu Calandria

David¹

2017

CNL Nuclear Review

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“…Combining eqs. (34) to (37), simple calculations lead to the following equation giving the interface temperature iterates T n+1,k 21 T n+1,k+1…”

Section: Stability Of a Toy Explicit Coupling Schemementioning

confidence: 99%

Solving Coupled Problems of Lumped Parameter Models in a Platform for Severe Accidents in Nuclear Reactors

Viot

Saas

Vuyst

2018

Int J Mult Comp Eng

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This paper focuses on solving coupled problems of lumped parameter models. Such problems are of interest for the simulation of severe accidents in nuclear reactors : these coarse-grained models allow for fast calculations for statistical analysis used for risk assessment and solutions of large problems when considering the whole severe accident scenario. However, this modeling approach has several numerical flaws. Besides, in this industrial context, computational efficiency is of great importance leading to various numerical constraints. The objective of this research is to analyze the applicability of explicit coupling strategies to solve such coupled problems and to design implicit coupling schemes allowing stable and accurate computations. The proposed schemes are theoretically analyzed and tested within CEA's PROCOR platform on a problem of heat conduction solved with coupled lumped parameter models and coupled 1D models. Numerical results are discussed and allow us to emphasize the benefits of using the designed coupling schemes instead of the usual explicit coupling schemes.

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“…These energy conservation equations are written in terms of the specific enthalpy of each layer. The evaluation of the heat fluxes at the layer boundaries rely on closures describing the boundary layer heat transfer in terms of heat transfer correlations (refer to [7] for examples). In addition, the models require a choice for formulating the energy conservation equations, depending on the enthalpy-temperature relations.…”

Section: Figure 1: Multilayer Corium Pool Descriptionmentioning

confidence: 99%

On the use of CALPHAD-based enthalpy-temperature relations in suboxidized corium plane front solidification modelling

Tiwari

Tellier

2018

Annals of Nuclear Energy

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The knowledge of in-vessel corium behaviour and associated risk of vessel failure are matters of prime interest within the framework of Severe Accident studies in a Light Water Reactor. Core meltdown during a severe accident results into formation of a corium pool at the bottom of the reactor vessel. This corium pool undergoes a density dependent liquid separation, thus exhibiting stratification into different phases. The distribution of phases depends on the time since the phase density depends on both temperature and composition of the phases. The evolution of stratification determines the impact of heat flux distribution at the lateral vessel wall, thereby determining the chances of success of the in-vessel retention strategy. Within integral codes, the modelling of corium behaviour involves the coupling between lumped parameter thermal models and thermochemical models. Integral thermal models consist of mass and energy conservation equations that require inputs related to thermochemical properties of the materials, which are closely related to the state variables. In particular, the closure of energy conservation equations requires enthalpy-temperature relations. In the framework of multicomponent systems, the dependence of such relations to chemical composition is of importance and should be treated adequately to obtain a more accurate description of the phases depicted by the model. An approach to do so is to keep a general formulation of energy conservation equations in terms of specific enthalpies instead of substituting simplified enthalpy-temperature relations on a case-by-case basis in order to obtain models with an explicit temperature formulation. The enthalpy-temperature relation is then considered as an "Equation-of-State" (EOS) that can be written as: H : T, (w j) j∈S → h along with its reciprocal relation T : h, (w j) j∈S → T where (w j) j∈S is the composition of the phase in terms of species mass fraction, h the mass enthalpy and T the temperature. The present study seeks to explore the use of CALPHAD-based enthalpy temperature relations in the modelling of suboxidized in-vessel corium plane front solidification. Along with theoretical considerations on the equations formulation, this paper discusses the numerical results based on a model developed in the PROpagation of CORium (PROCOR) platform interfaced with the Open-Calphad thermodynamic software.

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Natural convection heat transfer in corium pools: A review work of experimental studies

Cited by 67 publications

References 45 publications

Computational Fluid Dynamics Study of a Corium Pool in a Candu Calandria

Computational Fluid Dynamics Study of a Corium Pool in a Candu Calandria

Solving Coupled Problems of Lumped Parameter Models in a Platform for Severe Accidents in Nuclear Reactors

On the use of CALPHAD-based enthalpy-temperature relations in suboxidized corium plane front solidification modelling

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