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Proceedings of ICAPP ‘10 San Diego, CA, USA, June 13-17, 2010 Paper 10141 Interaction of Computational Tools for Multiscale Multiphysics Simulation of Generation-IV Reactors I.A. Bolotnov 1 , F. Behafarid 1 , D. Shaver 1 , T. Guo 2 , S. Wang 2 , H. Wei 2 , S.P. Antal 1 , K.E. Jansen 1 , R. Samulyak 2,3 , M.Z. Podowski 1* 1 Center for Multiphase Research, Rensselaer Polytechnic Institute; 2 Department of Applied Mathematics and Statistics, Stony Brook University 3 Computational Science Center, Brookhaven National Laboratory 110 8 th St., Troy, NY, U.S.A. * Tel: (518)276-4000, Email:[email protected] Abstract The objective of this paper is to discuss recent accomplishments in the development of advanced computer simulation capabilities for safety analyses of next-generation nuclear reactors. The proposed approach combines high performance computing with the necessary level of modeling detail and high accuracy of predictions. The results of multiscale simulations are shown of an accident scenario in a sodium-fast reactor, obtained using three interacting fluid dynamics codes, each performing simulations at a different scale: FronTier, PHASTA and NPHASE-CMFD. The loss-of-flow accident scenario results in the overheat and breach of the cladding of a stainless steel fuel, which results in the injection of pressurized fission gas into the molten sodium coolant. 1. INTRODUCTION It has been widely recognized that the development of next generation nuclear reactors, in particular - Gen. IV reactors, will require modeling and simulation tools which are much more accurate than those used so far by the nuclear industry, and are also capable of capturing a broad spectrum of multiscale physical phenomena governing reactor transients and accidents in a mechanistic manner. The development of a suite of high performance computational tools for multiscale simulations of the Gen- IV reactors has recently been undertaken by a DOE- sponsored university consortium. An important aspect of this project is concerned with simulating the phenomena leading to, and governing the progression of, core blockage accidents in the proposed Gen. IV Sodium Fast Reactors (SFR). The purpose of this paper is to present a 3-D modeling concept and its multi-code computer implementation, to simulate the injection of a jet of gaseous fission products into a partially blocked SFR coolant channel following localized cladding overheat and breach. Three computer codes have been used in the analysis, namely: FronTier, PHASTA and NPHASE-CMFD. The FronTier code has been used to model the heatup and melting of a nuclear fuel rod, failure of the rod‟s stainless steel cladding, and the escape of fission gases through the crack in the cladding. The output of FronTier simulations has been coupled with a fluid mechanics direct numerical simulation (DNS) code, PHASTA. The PHASTA code was coupled with a Level-Set model and used to simulate the injection of a two-phase fission gas jet into the coolant channel filled with liquid sodium. The time-dependent inflow shape and velocity profile of the fission gas is obtained from the FronTier results. The instantaneous velocity and gas concentration profiles were used to collect the necessary statistics downstream of the injection point, to provide multiphase inflow conditions for the Reynolds averaged Navier Stokes (RaNS) equations multiphase flow solver, NPHASE- CMFD. A three-dimensional model of gas/liquid-sodium interaction has been developed based on a multifield modeling framework implemented in the NPHASE-CMFD code. The NPHASE-based simulations were performed for a computational domain which was comparable in size with the geometry of complete interconnected reactor coolant channels. Details of the current multiscale multiple-solver modeling concept, as well as the results of predictions for a hypothetical channel blockage accident in the proposed sodium fast reactor are discussed below. 2. DESCRIPTION OF INDIVIDUAL COMPUTER CODES A. FronTier FronTier is a computational package for direct numerical simulation of multiphase flows [1] developed at Stony Brook University in collaboration with LANL and BNL. FronTier development and optimization for massively parallel supercomputers is a part of the DOE SciDAC program. An important and unique feature of this package is its robust ability to track dynamically moving fronts or material interfaces using the method of front

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Page 1: Interaction of Computational Tools for Multiscale ... · Interaction of Computational Tools for Multiscale Multiphysics Simulation of Generation-IV Reactors I.A. Bolotnov1, F. Behafarid1,

Proceedings of ICAPP ‘10 San Diego, CA, USA, June 13-17, 2010

Paper 10141

Interaction of Computational Tools for Multiscale Multiphysics

Simulation of Generation-IV Reactors

I.A. Bolotnov1, F. Behafarid

1, D. Shaver

1, T. Guo

2, S. Wang

2, H. Wei

2,

S.P. Antal1, K.E. Jansen

1, R. Samulyak

2,3, M.Z. Podowski

1*

1Center for Multiphase Research, Rensselaer Polytechnic Institute;

2Department of Applied Mathematics and Statistics, Stony Brook University

3Computational Science Center, Brookhaven National Laboratory

110 8th

St., Troy, NY, U.S.A. *Tel: (518)276-4000, Email:[email protected]

Abstract – The objective of this paper is to discuss recent accomplishments in the development of

advanced computer simulation capabilities for safety analyses of next-generation nuclear reactors.

The proposed approach combines high performance computing with the necessary level of modeling

detail and high accuracy of predictions. The results of multiscale simulations are shown of an accident

scenario in a sodium-fast reactor, obtained using three interacting fluid dynamics codes, each

performing simulations at a different scale: FronTier, PHASTA and NPHASE-CMFD. The loss-of-flow

accident scenario results in the overheat and breach of the cladding of a stainless steel fuel, which

results in the injection of pressurized fission gas into the molten sodium coolant.

1. INTRODUCTION

It has been widely recognized that the development of

next generation nuclear reactors, in particular - Gen. IV

reactors, will require modeling and simulation tools which

are much more accurate than those used so far by the

nuclear industry, and are also capable of capturing a broad

spectrum of multiscale physical phenomena governing

reactor transients and accidents in a mechanistic manner.

The development of a suite of high performance

computational tools for multiscale simulations of the Gen-

IV reactors has recently been undertaken by a DOE-

sponsored university consortium. An important aspect of

this project is concerned with simulating the phenomena

leading to, and governing the progression of, core blockage

accidents in the proposed Gen. IV Sodium Fast Reactors

(SFR).

The purpose of this paper is to present a 3-D modeling

concept and its multi-code computer implementation, to

simulate the injection of a jet of gaseous fission products

into a partially blocked SFR coolant channel following

localized cladding overheat and breach. Three computer

codes have been used in the analysis, namely: FronTier,

PHASTA and NPHASE-CMFD.

The FronTier code has been used to model the heatup

and melting of a nuclear fuel rod, failure of the rod‟s

stainless steel cladding, and the escape of fission gases

through the crack in the cladding. The output of FronTier

simulations has been coupled with a fluid mechanics direct

numerical simulation (DNS) code, PHASTA.

The PHASTA code was coupled with a Level-Set

model and used to simulate the injection of a two-phase

fission gas jet into the coolant channel filled with liquid

sodium. The time-dependent inflow shape and velocity

profile of the fission gas is obtained from the FronTier

results. The instantaneous velocity and gas concentration

profiles were used to collect the necessary statistics

downstream of the injection point, to provide multiphase

inflow conditions for the Reynolds averaged Navier Stokes

(RaNS) equations multiphase flow solver, NPHASE-

CMFD.

A three-dimensional model of gas/liquid-sodium

interaction has been developed based on a multifield

modeling framework implemented in the NPHASE-CMFD

code. The NPHASE-based simulations were performed for

a computational domain which was comparable in size with

the geometry of complete interconnected reactor coolant

channels.

Details of the current multiscale multiple-solver

modeling concept, as well as the results of predictions for a

hypothetical channel blockage accident in the proposed

sodium fast reactor are discussed below.

2. DESCRIPTION OF INDIVIDUAL COMPUTER

CODES

A. FronTier

FronTier is a computational package for direct

numerical simulation of multiphase flows [1] developed at

Stony Brook University in collaboration with LANL and

BNL. FronTier development and optimization for

massively parallel supercomputers is a part of the DOE

SciDAC program. An important and unique feature of this

package is its robust ability to track dynamically moving

fronts or material interfaces using the method of front

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Proceedings of ICAPP ‘10 San Diego, CA, USA, June 13-17, 2010

Paper 10141

2

tracking [2]. FronTier supports compressible and

incompressible Navier-Stokes equations and MHD

equations in the low magnetic Reynolds number

approximation [3], and phase transitions such as melting

and vaporization [4]. The FronTier code has been used for

large scale simulations of a variety of physical problems [3,

5, 6] on various platforms including the IBM BlueGene

supercomputer New York Blue located at Brookhaven

National Laboratory. The application of FronTier to the

present problem has been two-fold. First, it has been used

to model solid-state mechanics phenomena governing

cladding heatup and breach. Secondly, using the initial

conditions of pressurized fission gas inside the reactor fuel

pins prior to cladding failure, simulations have been

performed of gas flow through the cracked cladding.

B. PHASTA

PHASTA is a parallel, hierarchic (higher order

accurate from 2nd-5th order accurate depending on

function choice), unstructured/adaptive, stabilized (finite

element) transient analysis flow solver (both

incompressible and compressible) [7, 8]. PHASTA (and its

predecessor, ENSA) was the first unstructured grid LES

code [9] and has been applied to turbulent flows ranging

from validation benchmarks (channel flow, decay of

isotropic turbulence) to complex flows (airfoils at

maximum lift, flow over a cavity, near lip jet engine flows

and fin-tube heat exchangers). The PHASTA code uses

advanced anisotropic adaptive algorithms [10] and the most

advanced LES/DES models [11]. Note that DES, LES, and

DNS are computationally intensive even for single phase

flows. The two-phase version of PHASTA utilizes the

Level Set method to define the interface between the gas

and liquid phases [12]. Here, it has been used to simulate

gas jet injection into the coolant region using the boundary

conditions provided by FronTier. Turbulent two phase

PHASTA outflow is averaged over time to obtain mean

velocities for each phase, turbulent kinetic energy and

turbulence dissipation rate of each phase. This time-

averaged data provides the input to the next scale of the

simulation using the NPHASE-CMFD code. A sliding

window time averaging has been used to capture slow

changes to the mean flow parameters. Also, PHASTA

provides the pressure found at the inflow of its domain

back to FronTier outflow

C. NPHASE-CMFD

NPHASE-CMFD is an advanced Computational

Multiphase Fluid Dynamics computer program [14] for the

simulation and prediction of combined mass, momentum

and energy transfer processes in a variety of single-phase

[15] and multiphase/multiscale systems, including

gas/liquid [16, 17], solid/liquid [18, 19] and

gas/solid/liquid [14] flows. It uses two-phase k-ε models of

turbulence (the user can chose between the High Reynolds

Number and Low Reynolds Number options of the model).

In the present work, transient inflow boundary conditions

have been supplied by PHASTA to simulate fission-

gas/liquid sodium two-phase flow along and around the

failed fuel element and the elements adjacent to it.

NPHASE-CMFD also supplies the pressure value back to

the PHASTA domain outflow. Thus, all the three codes

used for the described multifield simulation are fully

coupled.

3. MODEL DESCRIPTION

3.1. Physical Problem

As it was mentioned before, a hypothetical channel-

blockage accident scenario in Gen-IV SFR has been used

as testing ground for the proposed approach of using three

interacting codes in multiscale simulations. Fig. 1 presents

an overview of the problem geometry. It has been assumed

that as a result of the accident, one of the fuel rods

overheats and causes a failure of the stainless steel

cladding. This results in fission gas injection into the

coolant.

Fig. 1. Geometry and dimensions of a section of SFR fuel

rod assembly with the cladding failure location.

The modeled phenomena include:

stainless steel failure mechanisms

pressurized fission gas escape from the fuel rod into

the liquid sodium coolant

two-phase side jet injection into the coolant

transient two-phase flow propagation downstream

from cladding failure

d = 10.4 mm

L ~

1.0

m

Overheated fuel rod

R = 4.0 mm

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Proceedings of ICAPP ‘10 San Diego, CA, USA, June 13-17, 2010

Paper 10141

3

3.2. Computational Domains

Figures 2 and 3 show the computational domain

sharing in the multiscale approach used in the simulations.

A description of the domain used by each of the three codes

and their interfaces in given next.

Fig. 2. Computational domains overview (side view).

Fig. 3. Top view of the computational domains for FronTier

and PHASTA.

FronTier computational domain

FronTier resolves detailed physics processes in the

computational domain that includes a 6 cm long section

around the hottest region of the fuel rod and a 1 cm thick

layer of the sodium coolant adjacent to the rod.

Computational grid use in the FronTier simulations of

cladding breach is shown in Fig. 4.

Fig. 4. Computational mesh in the FronTier simulations of

cladding breach.

PHASTA computational domain

The PHASTA domain is only about 1 cm tall, but it

includes the region around the cladding breach, which

overlaps with the FronTier domain, as well as section of the

coolant channel which starts below the breach and extends

to a short distance above the breach.

The finite element mesh used in PHASTA simulation

is shown in Fig. 5. It is characterized by the following

parameters:

Number of vertices: 2.145 million

Number of elements: 12.13 million

The gas flow rate computed by FronTier simulations is

used for setting up gas inflow boundary conditions in

PHASTA. Other boundary conditions are: no-slip boundary

conditions applied on all solid surfaces, and a pressure

boundary condition that corrects for the effects of surface

tension at the outflow of the domain. This outflow pressure

is supplied by the NPHASE flow solver.

NPHASE computational domain

The computational domain of NPHASE, shown in Fig.

2, actually encompasses and extends along, the coolant

channels around 30 fuel rods. This is shown in Fig. 6,

where the NPHASE domain overlays the PHASTA domain.

x

z

Overheated

Fuel Rod

Neighbor

Fuel Rod

Coolant

Inflow

NPHASE

Domain

PHASTA/NPHASE Interface

FronTier/PH

ASTA

interface PHASTA

Domain

Fission gas

FronTier

Domain

PHASTA

inflow

PHASTA

domain

y

z

FronTier

domain y

z

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Proceedings of ICAPP ‘10 San Diego, CA, USA, June 13-17, 2010

Paper 10141

4

Due to the symmetry of the problem and the ensemble

averaged nature of the NPHASE calculation, the data taken

from PHASTA is averaged across the symmetry line shown

in Fig. 6. The corresponding computational mesh in the

NPHASE simulations is shown in Fig. 7.

Fig. 5. Computational mesh used in PHASTA simulations.

Fig. 6. Cross section of the NPHASE domain showing

overlap with the PHASTA domain (blue) and the added

reactor channels (red). Arrow indicates the location of gas

jet. Solid line indicates the location of plots presented in

Fig. 19.

The mesh used in the NPHASE simulation is shown in

Fig. 7. It is axially non-uniform and consists of

approximately 500k elements. Since the NPHASE mesh is

much coarser than the PHASTA mesh, data is interpolated

from the PHASTA onto the NPHASE meshes to generate

the inlet conditions for the NPHASE simulation. The total

physical length of the NPHASE domain is 0.5m. This, in

turn, illustrates the advantages of coupling the DNS results

of PHASTA, limited for practical reasons to a relatively

small computational domain, with the NPHASE-based

large-scale model which uses accurate PHASTA

predictions as input.

Fig. 7. Computational mesh used in the NPHASE

simulations

3.3. Description of mathematical models

FronTier Models

The FronTier package has the ability to evaluate

moving fronts or material interfaces using the method of

front tracking. As shown in Fig. 8, the interfaces are

represented as lower dimensional meshes moving through a

volume filling grid. A volume-filling finite difference grid

supports smooth solutions located in the region between

interfaces. The dynamics of the interface comes from the

mathematical theory of the Riemann problem [20].

Fig. 8. Rectangular grid, interface, and states for the

method of front tracking. States contain density,

momentum, and energy density of the fluid, and references

to the EOS model and other parameters.

In the FronTier's solution algorithm [21], the Riemann

problem is solved for the left and right interface states to

predict the location and states of the interface at the next

time step. Then a corrector technique is employed which

accounts for fluid gradients on both sides of the interface.

FronTier can evolve and resolve topological changes of

a large number of interfaces in 2D and 3D spaces.

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Paper 10141

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Additional features of the FronTier hyperbolic solvers

include a choice of either exact or approximate Riemann

solvers and realistic models for the equation of state.

For the simulation of overheating and melting of the

nuclear fuel rod, new elliptic/parabolic solvers have been

developed, based on the embedded boundary method [4],

as well as an algorithm for the classical Stefan problem

describing first order phase transitions.

A new approach, based on the energy minimization of

the network of springs with critical tension, has also been

applied to develop new mesoscale models for the

simulation of fracture of inhomogeneous solid materials.

Such a description of solids makes it possible to avoid fast

time scales associated with acoustic waves and capture

important features of the material fracture. The main

emphasis has been on the study of brittle fracture. Two

regimes of the fracture have been considered: (a)

adiabatically slow deformation and breakup and (b)

instantaneously fast deformation and the formation and

propagation of cracks in stressed materials. The most

computationally intensive step in the algorithm is the

energy minimization. The methodology applied to both

constrained and unconstrained optimization problems is

done through the interface with TAO, a package developed

by Argonne National Lab within the DOE SciDAC

initiative.

Model testing included a comparison of the breakdown

stress with experimental data, studies of the breakdown

stress as a function of the probability of defects up to the

rigidity percolation threshold, and scaling of the

distribution function of the breakdown stress.

PHASTA models

The spatial and temporal discretization of the

Incompressible Navier-Stokes equations within PHASTA

has been described in Whiting and Jansen [7]. The strong

form of the INS equations is given by

Mass conservation

, 0i ju (1)

Momentum conservation

, , , ,ˆˆ ˆ

i t j i j i ij j iu u u p f (2)

where ρ is density, ui is the i-th component of velocity,

ˆ,p i is pressure, ˆ

ij is the stress tensor, and f̂i represents

body forces along the i-th coordinate.

For the incompressible flow of a Newtonian fluid, the

stress tensor is related to the strain rate tensor, Sij, as

, ,ˆ 2 ( )ij ij i j j iS u u (3)

Using the Continuum Surface Tension (CST) model of

Brackbill et al. [22], the surface tension force is computed

as a local interfacial force density, which is included in f̂i .

The stabilized finite element formulation used in the

PHASTA code [7] is based on the work of Taylor et al.

[23], Franca and Frey [24].

The level set method [12, 25, 26, 27] involves

modeling the interface as the zero level set of a smooth

function, φ, where φ represents the signed distance from the

interface. Hence, the interface is defined by φ = 0. The

scalar φ, the so-called first scalar, is convected within a

moving fluid according to,

. 0D

uDt t

(4)

where u is the flow velocity vector. Phase-1, typically the

liquid phase, is indicated by a positive level set, φ > 0, and

phase-2 by a negative level set, φ < 0. Evaluating the jump

in physical properties using a step change across the

interface leads to poor computational results. Therefore, the

properties near an interface are defined using a smoothed

Heaviside kernel function, Hε, given by:

,0

1 1 ,( ) 1 sin2

,1

H

(5)

The fluid properties are thus defined as

1 2( ) ( ) (1 ( ))H H (6)

1 2( ) ( ) (1 ( ))H H (7)

Although the solution may be reasonably good in the

immediate vicinity of the interface, the distance field may

not be correct throughout the domain since the varying

fluid velocities throughout the flow field distorts the level

set contours. Thus the level set is corrected with a re-

distancing operation [27].

NPHASE physical model

The multiphase model in the NPHASE-CMFD code is

based on the multifield modeling concept. The ensemble-

averaged mass and momentum equations, respectively, are

given by

Mass conservation

k k

k k k kt

v

(8)

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Momentum conservation

( )

( )

k k k

k k k k

i t

k k k kj k k k

j

t i i

k kj k kj k k

j j

t

p p p

vv v

M g

(9)

In Eqs.(8)-(9), (j,k) are the field indices, the subscript

„i‟ refers to the interfacial parameters,

i

kjM is the interfacial

force per unit volume exerted by field-j on field-k, and the

remaining notation is conventional.

The total interfacial force is formulated as a

superposition of several component forces

i D VM L TD

kj kj kj kj kj M M M M M (10)

where D

kjM is the drag force, is the VM

kjM virtual mass force,

L

kjM is the lift force, and TD

kjM is the turbulent dispersion

force.

The turbulence model in the NPHASE-CMFD code

accounts for both the continuous-field sheer-induced

turbulent viscosity and the dispersed-field(s)-induced

viscosity

turb SI BI

c c c (11)

The continuous field sheer-induced turbulence is

modeled using one of two versions of the k-e model: High

Reynolds Number (HRN) or Low Reynolds Number (LRN)

models. The dispersed-phase induced turbulence is based

on the model proposed by Sato & Sekoguchi [28].

3.4. Boundary conditions and interfaces between the

codes

To achieve coupling between the three codes used in

the analysis, a consistent data transfer must be provided

between the individual codes. A file-based data transfer

method has been used to provide multiphase inflow

boundary conditions for “downstream” software, using

additional processing, such as space and time interpolation

as well as averaging techniques when converting the DNS

results into RaNS inflow boundary conditions.

FronTier to PHASTA interface description

The FronTier crack formation simulation generates

mesh coordinates along with a connectivity array for the

crack shape at each time step of the crack growth

simulation. The PHASTA simulation uses this information

to block selected internal mesh nodes in its computational

domain, to dynamically change the effective crack size in

the two-phase flow simulation.

Since both FronTier and PHASTA provide

instantaneous velocity fields as their solutions, no

averaging of the data is required for this interface. The

following steps are taken to use the fission gas velocity

profile flowing though the failed stainless steel cladding

opening computed by FronTier as PHASTA inflow

boundary conditions:

Velocity distribution is recorded by FronTier in the

plane of interests

For each FronTier time step velocity profiles are

interpolated on the PHASTA mesh inflow nodes

During the PHASTA run the time-dependent velocity

profiles from FronTier are used as jet inflow

boundary conditions (linear time interpolation is

performed when PHASTA time step is smaller than

FronTier time step)

PHASTA to NPHASE-CMFD data transfer

The DNS results produced by the PHASTA code

require averaging before they can be used in NPHASE-

CMFD as inflow boundary conditions. The following

technique is used to provide the boundary conditions for

the NPHASE domain:

A list of coordinates at the NPHASE domain inflow is

generated.

At every time step of PHASTA execution

instantaneous velocity components (u1, u2, u3) and

distance to interface field are interpolated from

PHASTA solution at the NPHASE coordinates.

A postprocessing code performs the analysis of the

data and computes the mean velocity distribution

(U1k, U2

k, U3

k), volume fraction, turbulent kinetic

energy and turbulence dissipation rate, for each flow

field, k (e.g., k = 1for liquid and k = 2 for gas).

An example of velocity fluctuations along with gas phase

indicator function is shown on Fig. 9.

4. RESULTS

The models discussed in Section 3 have been used to

simulate the consequences of a loss-of-flow accident in a

Gen. IV Sodium fast reactor (SFR). The phenomena

modeled included: fuel element heatup, cladding heatup

and failure due to combined effects of thermal stresses and

fission gas pressure inside the fuel pin, injection of

pressurized fission gas into the coolant channels

surrounding the failed fuel element, and the transport of gas

/liquid-sodium mixture toward the top of the core. The

results of the multiscale simulations are presented next.

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Paper 10141

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-0.4

-0.2

0.0

0.2

0.4

0.6

0.8

1.0

1.2

1.4

0 0.02 0.04 0.06 0.08 0.1 0.12 0.14

ui,m/s

time, s

ui X2

Fig. 9. Example of DNS data produced by PHASTA for

two-phase flow at a fixed point which is used for obtaining

averaged data for NPHASE-CMFD (ui is velocity

components and X2 is the gas phase indicator function;

averaged values 1

1U and 2

1U are shown in blue and orange,

respectively).

4.1. FronTier Calculations

In the initial stage of FronTier simulations, heat

transfer was evaluated inside the hottest section of the fuel

rod with oxidic fuel. The calculated temperature

distribution across the fuel rod at normal operating

conditions is shown in Fig. 10. The predicted temperature

profile reflects the effect of thermal conductivity of both

the fuel and the cladding, as well as of the average thermal

conductance of the gas between the fuel pellets and the

inner cladding wall. The use of the embedded boundary

method for material interfaces was critical for achieving

accurate simulations of the heat transfer problem for such a

system.

Fig. 10. Temperature distribution across the fuel rod.

As a result of a reduced heat removal rate following

loss of coolant flow, the temperatures of both the fuel

material and the cladding wall start increasing. Figure 11

shows the increase of fuel temperature and the resultant

partial fuel melting in the central region of the hottest

pellet.

Fig. 11. Temperature distribution in the fuel rod during

transient overheating and melting of the fuel.

In the present case, the cladding fails before melting,

causing the ejection of fission gases into the coolant

channels. The increasing fuel temperature causes the

pressure inside the fuel rod to increase as well, thus

augmenting the mechanical load on the cladding wall. The

combined effects of elevated gas pressure and cladding

temperature weaken the cladding wall and eventually lead

crack formation. The predicted crack side is shown in 12.

Fig. 12. Formation of crack in the fuel rod cladding.

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Paper 10141

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In a separate FronTier simulation, the compressible

hydrodynamics front tracking code has been used to

simulate the ejection of fission gases into the sodium

coolant. To obtain the boundary conditions for the gas

pressure in the gap behind the crack, a porous medium

model was used, which resulted in a high pressure drop

between the gas storage volume and the near crack region

inside the fuel pin. The FronTier-calculated pressure

distribution in the crack region is shown in Figure 13.

Fig. 13. Isosurfaces of pressure of the fission gas escaping

the coolant through the crack in the cladding, calculated by

FronTier.

4.2. PHASTA Calculations

The PHASTA code has been used to simulate the

second scale of the multiscale problem. It used the gas

inlet information provided by FronTier. Fig. 14 shows the

gas velocity profile observed in PHASTA simulation inside

the stainless steel cladding failure zone. Fig. 15 shows an

instantaneous velocity profile for a 3D simulation of a gas

jet entering the liquid sodium coolant flow.

Fig. 14. Velocity profile of fission gas injected into the

reactor coolant channels, calculated by PHASTA.

A three-dimensional view of the instantaneous

PHASTA solution is shown in Figs. 15 and 16. The top

surface of the domain shown in Fig. 16 is the

PHASTA/NPHASE interface plane where the flow

statistics are collected in order to provide inflow conditions

for the NPHASE run.

(a)

(b)

Fig. 15. 3D two-phase PHASTA simulation of fission gas

jet entering the coolant flow. This Figure shows both the

velocity magnitude and gas/liquid interface contours: (a)

side view, (b) top view.

Fig. 16. Instantaneous PHASTA velocity field with the

NPHASE interface plane shown at the top. The gas/liquid

interface is marked with a solid black line.

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Paper 10141

9

The present two-phase PHASTA simulation was

performed on 2,048 IBM BlueGene/L processors for about

180 wall clock hours, which corresponds to approximately

370,000 CPU-hours.

Fig. 17. (a) U velocity component of liquid phase; (b) U

velocity component of gas phase; (c) volume fraction of the

gas phase in the NPHASE solution (inlet at right, outlet at

left, equally-spaced intervals in between).

4.3. NPHASE-CMFD Calculations

The NPHASE-CMFD code has been used to simulate

the largest scale of the present multi-scale problem. The

data has been collected at a cross plane in the PHASTA

domain and used at the inlet of the NPHASE simulation.

The inflow data taken from the PHASTA simulation has

been applied to the blue region shown in Fig. 6. For the

inlet condition used in the NPHASE domain in the regions

not covered by the PHASTA simulation, a fully developed

turbulent profile has been used matching the coolant mass

flux specified by PHASTA. This profile has been

calculated using the NPHASE code.

The NPHASE model tracks the velocity fields of the

gas and liquid phases independently. These can be seen in

Figs. 17(a) and 17(b). The complex inlet flow pattern is a

direct result of large scale eddies produced by the jet

hitting the neighboring fuel rods. These are long standing

fluid structures which are not eliminated by the time

averaging done on the PHASTA data. Downstream from

the jet, these structures decay into a much less chaotic flow.

The NPHASE-CMFD model has been used to

determine how the gas released into the coolant spreads as

it travels along the coolant channel. Figs. 17(c) and 18

show how the volume fraction of gas changes along the

reactor channel. The turbulent dispersion force causes it to

spread out over a significant portion of the channel cross

section. Fig. 19 presents the line plots of the volume

fraction of gas taken at various locations along the coolant

flow. It can be seen how the gas redistributes itself before

being dispersed. As can be seen in Fig. 17, the gas velocity

increases along the channel due to gravity. This causes a

drastic drop in volume fraction which is observed in the

initial section of the channel.

Fig.18. 3D computational domain showing the gas

volume fraction predicted by NPHASE-CMFD. The inlet

is at the bottom right, the outlet at top left.

5. SUMMARY AND CONCLUSIONS

A multiscale modeling approach to the analysis of

nuclear reactor transients and accidents has been discussed.

It has been demonstrated that by using multiple computer

codes in a coupled mode, a broad range of phenomena

governing accident progression can be simulated in a

physically-consistent and numerically accurate manner.

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Proceedings of ICAPP ‘10 San Diego, CA, USA, June 13-17, 2010

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ACKNOWLEDGMENTS

The authors would like to acknowledge the financial

support provide to this study by the U.S. Department of

Energy and the computation resources provided by the

Computational Center for Nanotechnology Innovations

(CCNI) at Rensselaer Polytechnic Institute (RPI).

Fig. 19. NPHASE-CMFD-predicted distribution of gas

volume fraction (plots taken along solid line shown in

Fig. 6) for various streamwise locations given in legend..

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