overview of the bison multidimensional fuel performance code · pdf file ·...

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Overview of the BISON Multidimensional Fuel Performance Code

Rich Williamson

BISON Team

Jason Hales, Steve Novascone, Ben Spencer,

Danielle Perez, Giovanni Pastore

IAEA Technical Meeting: Modeling of Water-Cooled Fuel

Including Design-Basis and Severe Accidents

October 28 – November 1, Chengdu, China

Outline

• Background

• Code Verification and Validation

• Applications in 3D

– Missing Pellet Surface

– Halden IFA-431 Rod 4 (eccentric vs concentric pellets)

• Priorities for the Future

• Summary

MOOSE-BISON-MARMOT

Multiphysics Object-Oriented Simulation Environment

Atomistic/Mesoscale Material

Model Development

• Predicts microstructure

evolution in fuel

• Used with atomistic methods

to develop multiscale

materials models

• Simulation framework allowing rapid

development of FEM-based applications

Advanced 3D Fuel Performance

Code

• Models LWR, TRISO and metal

fuels in 1D, 2D and 3D

• Steady and transient reactor

operations

• The MOOSE-BISON-MARMOT codes provide an advanced, multiscale

fuel performance capability

Fuel Performance Code

Solution method: Implicit finite element solution of the coupled thermomechanics and species diffusion equations using the MOOSE framework

Multiphysics constitutive models: large deformation mechanics (plasticity and creep), cracking, thermal expansion, densification, radiation effects (swelling, thermal conductivity, etc.).

Massively

parallel, has

been run on

1 - 12,000

cpus.

Substantial experimental

validation is underway

R. L. Williamson, J. D. Hales, S. R. Novascone, M. R. Tonks, D. R. Gaston, C. J. Permann, D.

Andrs and R. C. Martineau, “Multidimensional Multiphysics Simulation of Nuclear Fuel

Behavior,” Journal of Nuclear Materials, 423, 149 (2012)

• Energy conservation (transient heat conduction with fission source)

• Species conservation (transient oxygen or fission product diffusion with

radioactive decay)

• Momentum conservation (Cauchy’s equation of equilibrium)

BISON Governing Equations

FETkt

Tc fp

)(

SCTFRT

CQCD

t

C

2

*

Fission density rate = f(x, t)

Fickian diffusion

Soret diffusion

Radioactive decay

BISON LWR Capabilities

Oxide Fuel Behavior

• Temperature/burnup dependent conductivity

• Heat generation with radial and axial profiles

• Thermal expansion

• Solid and gaseous fission product swelling

• Densification

• Thermal and irradiation creep

• Fracture via relocation or smeared cracking

• Fission gas release (two stage physics)

transient (ramp) release

grain growth and grain boundary sweeping

Cladding Behavior

• Thermal expansion

• Thermal and irradiation creep

• Irradiation growth

• Gamma heating

• Combined creep and plasticity

Gap/Plenum Behavior

• Gap heat transfer with kg= f (T, n)

• Mechanical contact (master/slave)

• Plenum pressure as a function of:

evolving gas volume (from mechanics)

gas mixture (from FGR model)

gas temperature approximation

General Capabilities

• Finite element based 1D spherical, 2D-RZ and 3D fully-coupled thermo-mechanics with species diffusion

• Linear or quadratic elements with large deformation mechanics

• Steady and transient operation

• Massively parallel computation

• Meso-scale informed material models

Temperature

Coolant Channel

• Closed channel thermal hydraulics with heat transfer coefficients

What makes BISON different?

Parallel Computing

CPU 0 CPU 2 CPU 1

Some tasks are embarrassingly

parallel meaning that they do not

require any communication.

For example,

taking the square root of a list of

numbers.

However, most parallel computing

requires communication.

For example, summing a list of

numbers.

Results – Missing Pellet Surface

displacements magnified 25x

• MPS defect results in higher pellet temperatures and much higher clad stress; need for 3D analysis is clear

Simulation of Aspherical TRISO Particle

• Aspherical particles are fairly common

• Single facet aspherical particle problem has been

solved in BISON assuming 2D axisymmetry

200 mm

Time (Ms)

Ta

ng

en

tia

l S

tre

ss

(M

Pa

)

0 20 40 60 80-600

-400

-200

0

200

400

600Aspherical

Spherical

• During accident testing, asphericity raises peak

tensile stress in SiC containment layer by almost 4x

• Typical run times of a few minutes on 8 processors

Time

Te

mp

era

ture

(K

)

500

2000

1500

1000

Irradiation

2.5 yrs

12% FIMA

Step 1

Storage

100 days

Step 2

Furnace

Heating

200 hrs

Step 3

2073 K

300 K

Time (sec)

Th

erm

al

Co

nd

uct

ivit

y (

W/m

/K)

0 20000 40000 60000-0.5

0

0.5

1

1.5

2

2.5

3

AEH_x

AEH_y

Direct_x

Direct_y

Thermal Conductivity from MARMOT

• The direct method is sensitive to bubbles

on the boundary

• Boundary bubbles result in low local

temperature

• This results in a low average temperature

and thus a low thermal conductivity

• The AEH technique is not sensitive to

local effects

Temperature from the direct approach with flux applied in the x (left) and y (right)

directions. Note areas of low temperature in the x-direction plot.

3D/Arbitrary Geometry Parallel Computing

Coupling Fuel Types

Outline

• Background






• Summary

Verification, Validation, and Uncertainty Analysis

Beginning of life temperature validation Calibration of relocation model using DAKOTA

• BISON and associated software is supported by extensive

regression testing (>800 tests for BISON thru MOOSE)

• Validation to a wide variety of integral rod tests in progress

• BISON has been coupled with SNL’s DAKOTA code for

systematic sensitivity analysis and uncertainty quantification

DAKOTA

BISON

response

metrics parameters

BISON Code Assessment Comparisons to integral fuel rod data (21 rods, ~ 35 measurements)

Experiment Rod FCT - BOL FCT – TL

FCT -

Ramps FGR Clad - Elong

Clad – Dia

(PCMI)

IFA-431 1, 2, 3 X

IFA-432 1, 2, 3 X X

IFA-513* 1, 6 X X

IFA-515.10 A1 X X

IFA-597.3 7 X X

IFA-597.3* 8 X

RISO-3* AN3 X X

RISO-3* AN4 X X

FUMEX-II 27(1) X

FUMEX-II 27(2a) X

FUMEX-II 27(2b) X

FUMEX-II 27(2c) X

RISO-3 GE7 X X

OSIRIS J12 X

REGATE X X

IFA-431 (3D) 4 X

*Early User Assessment problems

D. M. Perez, R. L. Williamson, S. R. Novascone, T. K. Larson, J. D. Hales, B. W. Spencer and G. Pastore, An Evaluation

of the Nuclear Fuel Performance Code BISON, Int. Conf. on Mathematics and Computation Applied to Nuclear Science &

Engineering (M&C 2013) Sun Valley, Idaho, May 5-9, 2013.

Beginning of Life Fuel Centerline Temperature

• Very good

comparisons for

the eleven

measurements

considered to date

• BOL comparisons

validate important

physics such as

power input, fuel

and clad thermal

conductivity, gap

gas conductivity,

fuel and clad

thermal expansion,

gap closure and

fuel relocation

RISØ-AN3 Power Ramp

Fuel Centerline Temperature Fission Gas Release

• Base irradiated in the Biblis A PWR over four reactor cycles. Re-fabricated rod was shortened and

instrumented with a fuel centerline thermocouple and pressure transducer.

• Ramp tested at the RISØ DR3 water-cooled HP1 rig

• Assumed short rod length through base irradiation and ramp

RISØ-3 GE7 – PCMI During Power Ramp • Base irradiated in the Quad Cities-1 BWR for ~5 years; Ramp tested in the RISØ DR3 water-cooled

HP1 rig under BWR conditions

• 72-pellet stack modeled in axisymmetry with discrete pellets

• Strong axial power profile during ramp test

Outline

• Background






• Summary

Zr-4

clad

He fill gas

Missing pellet

surface

UO2

fuel

PCMI - Missing Pellet Surface Analysis

• High resolution 3D calculation (250,000 elements, 1.1x106 dof) run on 120 processors

• Simulation from fresh fuel state with a typical power history, followed by a late-life power ramp

Cross-section of rod that

failed due to MPS defect

(from Aleshin et al, 2010)

Results – Temperature

(a) pellets and cladding (b) only cladding shown (deformations magnified

15x)

0.25 mm

deep defect

0.5 mm

deep defect

0.25 mm

deep defect 0.5 mm

deep defect

Results – Clad Creep Strain

0.25 mm

deep defect

0.5 mm

deep defect

Zoomed-in view of 0.5 mm deep defect

• Creep during base irradiation plays significant role in relaxing

stresses

Results – Frictionless vs. Glued

Frictionless Glued Contact

• 0.5 mm defect model run with glued contact to determine the effect of contact

friction coefficient on stresses

• Friction coefficient has strong influence on stresses in defect region

• Frictionless and glued contact are bounding cases – frictional contact is

clearly needed, and is a current development effort

IFA-431 Rod 4 – Concentric vs. Eccentric Pellets

• Several pellets locked in position (radially) by oversize pellets, thermocouples and Mo rods

• Top section held concentrically; Bottom section held eccentrically

• Rod Fill gas – 100% Xe

IFA-431 – Model Geometry Modeled as two separate shortened rods, with a single larger-diameter pellet at the top

and bottom. The four-pellet test section is modeled as a single smeared column. In

both cases, the thermocouple sheath and moly rods were centered in the larger-

diameter pellets. In the eccentric case, the test pellets are shifted radially as shown.

IFA-431 – Relocation Activation Study

• Original predicted temperatures

(green) clearly follow trends in the

experimental data (concentric

hotter than eccentric), but the

differences increase with increasing

power.

• The simple empirical relocation

model in BISON activates at 19.7

kW/m. As a parametric study, the

relocation activation energy was

simply reduced by a factor of two

(9.85 kW/m) and four (4.93 kW/m),

with the results plotted here.

• Other more rigorous studies also

point to the need for a lower

activation power.

• Better comparisons are obvious for

lower activation power.

xxxx

xxx

x

xx

xx

xx

xx x

x xx

x xxx

ALHR (W/m)

Te

mp

era

ture

(C

)

0 5000 10000 15000 200000

500

1000

1500

2000 BISON-Xe Concentric (19.7 kW/m activation)

BISON-Xe Concentric (9.85 kW/m activation)

BISON-Xe Concentric (4.93 kW/m activation)

BISON-Xe Eccentric (19.7 kW/m activation)



Halden-Xe Concentric

Halden-Xe Eccentric

x

Error bars are

+/- 5% power uncertainty

IFA-431 – BOL Fuel Centerline Temperature

• Shown is a comparison of

predicted temperatures for

the concentric and eccentric

rods at a LHGR of 20 kW/m.

• The peak temperature for

eccentrically positioned

pellets is clearly lower than

for concentric pellets

• Additionally, in the eccentric

case, the thermocouple is

not sensing the highest

temperature region in the

fuel. Clad inner wall temperature:

547 547

553 596

AP-1000 Preliminary Simulation

Temperature and magnified displacement results for an AP1000 core

Each rod shown is a unique BISON simulation Temperature and magnified displacement results for an AP1000 core



Each rod shown is a unique BISON simulation

Temperature and magnified displacement results for an AP1000

core. Each rod shown is a unique BISON simulation.

Loosely

coupled:

• BISON

• RattleSnake

• R7

• Marmot

Outline

• Background






• Summary

Path Forward – Validation and UQ

• Completed: ~ 20 LWR cases, 13 TRISO cases

• Many, many more are needed; major emphasis for FY-14

- FUMEX-II and -III priority cases

- Halden collaboration

- NNL collaboration on ENIGMA cases

• Participation in FUMAC

• Develop systematic approach to frequently run and compare all

cases and update documentation

• Sensitivity analyses and UQ studies – DAKOTA and RAVEN

Modeling Accident Behavior (RIA and LOCA)

• Much of the required framework is in place:

– Transient operators with adaptive time stepping

– Arbitrary geometry with large deformation mechanics

– Implicit numerics with fully coupled physics

– Fission gas coupled to swelling

• Development areas:

– Multiphysics coupling

Neutronics (RIA)

Thermal-fluids (LOCA)

– Fuel material behavior

Fission gas burst model

Novel fracture models for extensive fuel cracking

Nakamura et al., 2000

Nakamura et al., 2000

Modeling Accident Behavior - continued

– Clad material behavior

Temperature and strain rate

dependent plasticity models

Rapid steam oxidation, with

a moving material interface

Hydrogen diffusion and

embrittlement

High temperature creep

and plasticity

Ballooning (large plasticity)

and burst (failure models

and discrete fracture via

XFEM)

BISON Release and Documentation

• Code Release (Ver 1.0) on Sept. 30, 2013

• Theory, User and Assessment Manuals

• Journal and Conference Papers (2013)

1. J. D. Hales, R. L. Williamson, S. R. Novascone, D. M. Perez, B. W. Spencer, and G. Pastore, “Multidimensional

Multiphysics Simulation of TRISO Particle Fuel,” J Nuc Mat, in press (2013).

2. M. C. Teague, M. R. Tonks, S. R. Novascone, and S. R. Hayes, “Microstructural Modeling of Thermal Conductivity

of High Burnup Mixed oxide Fuel,” J Nuc Mat, in press (2013). 3. M. R. Tonks, P. C. Millett, P. Nerikar, S. Du. D. Andersson, C. R. Stanek, D. Gaston, D. Andrs, and R. Williamson, “Multiscale

Development of a Fission Gas Thermal Conductivity Model: Coupling Atomic, Meso and Continuum Level Simulations,” J Nuc Mat, 440,

193-200 (2013).

4. J. D. Hales, M. R. Tonks, M. R. Chockalingam, D. M. Perez, S. R. Novascone, and B. W. Spencer, “Multiscale Nuclear Fuel Analysis via

Asymptotic Expansion Homogenization,” Transactions of SMiRT-22, San Francisco, California, 18-23 August 2013. 5. S. R. Novascone, B. W. Spencer, R. L. Williamson, D. Andrs, J. D. Hales, and D. M. Perez, “The Effects of Thermomechanics Coupling Strategies in Nuclear Fuel

Performance Simulations,” Transactions of SMiRT-22, San Francisco, California, 18-23 August 2013.

6. F. N. Gleicher, S. R. Novascone, B. W. Spencer, R. L. Williamson, R. C. Martineau, M. Rose, and T. Downar, “Coupling the Core Analysis Program DeCART to the

Fuel Performance Program BISON, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and

Engineering, Sun Valley, Idaho, 5-9 May 2013. 7. J. D. Hales, D. Andrs, and D. R. Gaston, “Algorithms for Thermal and Mechanical Contact in Nuclear Fuel Performance Analysis,” Proceedings of the International Conference on

Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, 5-9 May 2013.

8. D. M. Perez, R. L. Williamson, S. R. Novascone, T. K. Larson, J. D. Hales, B. W. Spencer, and G. Pastore, “An Evaluation of the Nuclear Fuel Performance Code BISON,” Proceedings of

the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, 5-9 May 2013.

9. S. R. Novascone, B. W. Spencer, D. Andrs, R. L. Williamson, J. D. Hales, and D. M. Perez, “Results from Tight and Loose Coupled Multiphysics in Nuclear Fuels Performance

Simulations using BISON,” Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, 5-9

May 2013.

10. L. P. Swiler, R. L. Williamson, and D. M. Perez, “Calibration of a Fuel Relocation Model in BISON,” Proceedings of the International Conference on Mathematics and Computational

Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, 5-9 May 2013.

11. J. D. Hales, D. M. Perez, R. L. Williamson, S. R. Novascone, B. W. Spencer, and R. C. Martineau, “Validation of the BISON 3D Fuel Performance Code: Temperature Comparisons for

Concentrically and Eccentrically Located Fuel Pellets,” Enlarged Halden Programme Group Meeting: Proceedings of the Fuels and Materials Sessions, Storefjell Resort Hotel, Norway,

10-15 March 2013.

Summary

• BISON is being leveraged across multiple US-DOE programs and is

in use at multiple national and international laboratories, many

universities and in industry

• User base is expanding… user support efforts are significant

• Roughly 20 integral rod LWR and 13 TRISO validation cases have

been completed… many more are needed

• BISON used to do first-ever simulation of 3D pellet eccentricity

experiment (invited paper at Halden Reactor Program Meeting)

• Major new capability completed for TRISO-coated particle fuel

• Numerous new applications (metal plate fuel, fast reactor oxide fuel,

accident tolerant fuel designs, ATR experiment design)

demonstrate BISON’s versatility

• First official code release was September 30, 2013

FCRD

30

The National Nuclear Laboratory

31

Individual

Applications

Common fuels

related physics

Common non-fuels

related physics

Animal Hierarchy

MOOSE

ELK

FOX

Peregrine BISON

Common component interface

and solution scheme

RISO-3 AN3 • FUMEX-II Priority Case

• Fuel pin CB8 was base irradiated in the Biblis A PWR over four reactor cycles

• Re-fabricated fuel pin (CB8-2R) was shortened from the CB8 rod and

instrumented with a fuel centerline thermocouple and pressure transducer.

• CB8-2R was ramp tested at the Riso DR3 water-cooled HP1 rig

• Assumed short rod length through base irradiation for simulation

• Modeled as 2D-RZ axisymmetric with smeared pellets; Quadratic elements

Aspect ratio scaled 10x

RISO-3 GE7 – PCMI • FUMEX-III Priority Case

• Fuel segment ZX115 base irradiated in the

Quad Cities-1 BWR for ~5 years

• Ramp tested in the Riso DR3 water-cooled HP1

rig under BWR conditions

• 72-pellet stack was modeled as 2D-RZ

axisymmetric with individual (discrete) pellets;

quadratic elements

• Strong axial power profile during ramp test

Zr-2 clad

He fill gas (0.29 MPa)

110 mm gap

UO2 fuel

radius expanded 6x

RISO-3 GE7 – Continued

100 s ramp

Results – Missing Pellet Surface

displacements magnified 25x

• MPS defect results in higher pellet temperatures and much higher clad stress; need for 3D analysis is clear

Path Forward – Enhanced Oxide Fuel Capabilities

• Fuel fracture (smeared and discrete)

• Thermomechanical contact

• Material model development

- Fuel creep

- Solid swelling

- Clad behavior – coupling primary/secondary creep to instantaneous plasticity

- High burnup fuel structure (with coupling to Marmot and MAMMOTH)

• General restart

HBS Micrographs, Photos courtesy of Glyn

Rossiter, National Nuclear Laboratory

Smeared cracking Discrete cracking

IFA-431 Eccentricity Study

The precise radial location of the eccentric pellets is not clear in the above description, which was extracted

from the report NUREG/CR-0560 (PNL-2673). Note that for the concentric portion of the rod, the radial

pellet-clad gap for the standard diameter pellets is 114 mm. However the drawing indicates the pellets were

displaced radially 127 mm in the eccentric case, which would place them beyond the inner wall of the clad.

IFA-431 – Eccentricity Study, Continued

• Since the precise radial location of the eccentric pellets was unknown, an additional parametric study involved varying the location of the eccentric pellets from flush with the larger pellets to 10 and 20 mm less than flush.

• For the non-flush cases, the fuel pellets were moved inward thus increasing the local pellet-clad gap.

• The results show the expected effect of varying eccentricity and seem to indicate that the level of eccentricity is irrelevant once the test pellets come into contact with the clad.

• Relocation activation level was 4.9 kW/m per prior parametric study.

ALHR (W/m)

Te

mp

era

ture

(C

)

0 5000 10000 15000 20000 25000200

400

600

800

1000

1200

1400

BISON - Flush

BISON - 10 mm off

BISON - 20 mm off

HALDEN

Error bars are

+/- 5% power uncertainty

User Training

Workshop Materials

• ~ 200 slides

• Overview, Getting Started, Theory, Example Problem, Mesh Generation, Post Processing, Adding a New Material

BISON 2-day Workshops

• INL – January 2012

• MIT – January 2012

• Anatech – Feb 2012

• INL – May 2012 (23 participants)

• NNL (UK) – September 2012

• INL – December 2012 (15 participants)

• INL – June 2013 (11 participants)

• WEC – Aug 2013 (10 participants)

• INL – Dec 2013 (planned)

overview of the bison multidimensional fuel performance code · pdf file ·...

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