coupled thermal-hydraulics/neutronics code, mars/master
TRANSCRIPT
-1/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Coupled Thermal-Hydraulics/Neutronics Code, MARS/MASTER
June 17, 2005
Presented at the 1st Workshop on PBMR Coupled Neutronics/Thermal-Hydraulics Transient Benchmark,
the PBMR-400 Core Design
Prepared by
J.-J. Jeong*, W. J. Lee, K. S. Kim, J. M. Noh, H. K. Joo(*[email protected])
Korea Atomic Energy Research Institute
-2/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Outline
The Coupled Thermal-Hydraulics/NeutronicsCode, MARS/MASTER- Thermal-Hydraulic System Code, MARS- Neutronics Code, MASTER- Coupled Code, MARS/MASTER
Improvement of MARS/MASTER for GCR Applications- Development of MARS-GCR- Improvement of MASTER for GCR Applications- MARS/MASTER-GCR
-3/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
*MARS: Multi-dimensional Analysis of Reactor Safety.
The Coupled Thermal-Hydraulics/NeutronicsCode, MARS/MASTER- Thermal-Hydraulic System Code, MARS*- Neutronics Code, MASTER- Coupled Code, MARS/MASTER
Improvement of MARS/MASTER for GCR Applications- Development of MARS-GCR- Improvement of MASTER for GCR Applications- MARS/MASTER-GCR
-4/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Best-Estimate T/H System Code, MARS*– Developed by KAERI Since 1997
– Best-Estimate Analysis of LWR T/H System Transient– Supported by Long-term Nuclear R&D Program– Main Structures: RELAP5/MOD3 (1D Module) and
COBRA-TF (3D Module)– MARS Code Development Activities
• Improvement and Extension of T/H Modeling Capabilities• Code Couplings • Restructuring of Data Structure (Fortran90, More than 40%
Rewritten)• GUI on Windows System (QuickWin and NPA Versions)
The MARS Code Development
*J.-J. Jeong, K.S. Ha, B. D. Chung and W.J. Lee, ”Annals of Nuclear Energy, vol. 26, no. 18, pp. 1161-1642 (1999).
-5/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
New component• Multi-D porous media equations• R-θ and Cartesian coordinatesMulti-D Hydrodynamics
Option in 1D/3D module• Viscous shear term in momentum eq.Viscous Shear
Option in 3D module• Liquid film dryout in annular flowMechanistic Dryout
Option in 1D module• NE/NH model for bubbly flow
derived from system Characteristics Eq.
Critical Flow
Under V&V• Interfacial area, heat transfer and
steam penetration in sonic jet flow regime
Direct Contact Condensation in Condensation Tank
Under implementation• Incorporation of droplet field in 1D module
Droplet Field in 1D Module
Option in 1D module• Stability enhancing interfacial pressure force model
Improved Numerical Method
Default in 3D moduleUnder further development
• Interfacial drag and heat transfer in inverted pool flow regimeDirect Vessel Injection
Implementation StatusMajor ImprovementsT/H Models
Improvement of the MARS T/H Models
-6/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Option in 1D module
• Horizontal flow regime map• Fuel heat-up in stratified flow• Digital sampling model• Spray flow regime model• CANDU decay heat • EM critical flow
CANDU
Option in 1D module• Helical SG heat transfer• Critical heat flux• Critical flow with non-condensable
SMART
Option in 1D module• Heat transfer packageHANARO
Option in 1D/3D moduleUnder V&V
• Thermodynamic and transport properties of He and CO2
• Heat transfer package for gas flowGas-Cooled Reactor
Option in 1D module• Heat transfer correlationsTight Lattice Core
Implementation StatusMajor ImprovementsT/H Models
Extension of the MARS T/H Models
-7/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
RELAP5/MOD3 + COBRA-TF*Three-Dimensional Reactor Kinetics Code, MASTER, which contains the COBRA-III/CP Subchannel AnalysisModuleContainment Analysis Code, CONTEMPT4 andCONTAIN
*Thermal-Hydraulic Code for the Reactor vessel T/H and Subchannel Analysis
Coupled Analysis Capability of MARS
-8/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
GUI: QuickWin or NPA
3D Module(COBRA-TF)
1D Module(RELAP5)
Internal, Implicit Coupling – Consolidation
External, ExplicitCoupling with DLL
CONTEMPT & CONTAIN
MASTER &COBRA-III/CP
MARS Code Structure
-9/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
The MASTER Code (I)Core Neutronics Design and Analysis Code Developed by KAERI– Three-dimensional, Two-group Neutron Diffusion Equations– Core Reactivity and Pin-wise Power Distribution Calculation with T/H
Feedback– Coupled to HELIOS and CASMO Generated Cross Sections– Depletion Calculation with Microscopic Cross Sections– Xe Dynamics Calculation– Transient Calculation with COBRA-III/C T/H Module– Verified Against Critical Experiments and Plant Measured Data
• B&W Criticals• 14 Cycles including YGN1, YGN3, Palo Verde
Additional Features– Hexagonal Geometry Handling (Base = Rectangular)– Various Solutions Kernels (NEM, ANM, AFEN, TPEN)– Multigroup Calculation Possible for Block Type VHTR– QuickWin Graphics for Online Transient Plots
*Multi-purpose Analyzer for Static and Transient Effects of Reactors
-10/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
The MASTER Code (II)
-11/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
MARS/MASTER MARS/MASTER/COBRAMARS/MASTER MARS/MASTER/COBRA
MASTER3D KineticsModule
RELAP5:Coolant System
COBRA-TF:Reactor Vessel
COBRA IIISub-channelModule
MASTER
ρi & TFi at tj
Local powers at tj
Refined ρi & TFi at tj
tj-1
Core inlet flows &exit pressures at tj
MASTER:3D KineticsModule
1D (RELAP5)Coolant System
3D(COBRA-TF)Reactor Vessel
COBRA-III/CP:Core T/H & DNBR
i
tj-1
MARS Core inlet flows &exit pressures at t
Single Coupling Double Coupling
Refined coreT/H nodalization
Subchannel module
CONTAIN &CONTEMPT
Local powers at
MARS/MASTER Code Coupling
*H. G. Joo, J.-J. Jeong, B. O. Cho, W. J. Lee, and S. Q. Zee, “Analysis of the OECD MSLB Benchmark Problem using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code,” Nuclear Technology, vol. 142, pp. 166-179 (2003).
Explicitly Coupled with Dynamic Link Library (DLL) TechniqueTwo Coupling Schemes: Single & Double Coupling Scheme*
-12/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Conceptual ProblemsConceptual Problems
The OECD/NEA MSLB Benchmark ProblemThe OECD/NEA MSLB Benchmark Problem
0 20 40 60 80 1000.0
0.2
0.4
0.6
0.8
1.0
1.2
Nor
mal
ized
cor
e po
wer
Time (s)
A B C D E F G H I KAERI
V&V of the Coupled Code
Radial Power at 67.2 s
Intact side
Broken side
Total Core Power Behavior
-13/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
MARS/MASTER has been developed for LWRs.
In the PBMR, the coolant is gas, the moderator is graphite, and …
-14/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
The Coupled Thermal-Hydraulics/NeutronicsCode, MARS/MASTER - Thermal-Hydraulic System Code, MARS- Neutronics Code, MASTER- Coupled Code, MARS/MASTER
Improvement of MARS/MASTER for GCR Applications- Development of MARS-GCR- Improvement of MASTER for GCR Applications- MARS/MASTER-GCR
-15/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Development of MARS-GCR
T/H Modeling Requirements for GCR Applications*
M3-D Kinetics/ContainmentCoupled Analysis
--AvailableRadiation Heat Transfer
HN/A, GAMMAGraphite Chemical Reaction
MN/ASystem Component Models
MN/AMulti-D Heat Conduction
HMULTI-D ComponentMulti-D Hydrodynamics
HN/AContact Heat Transfer
HSimple Model at Low ReConvection Heat Transfer
HSimple NC gas in VaporGas Flow & Properties
PriorityMARS CapabilityT/H Models
H: High, M: Medium
Developed
Modified
DevelopedDeveloped
To be develope
To be develope
To be develope
To be develope
OK
*W. J. Lee et al., “Development of MARS-GCR/V1 and its Application to Thermo-Fluid Safety Analysis of Gas-Cooled Reactors,” ICAPP 2005, Seoul, Korea, May 2005.
-16/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Gas Flow & Properties
He and CO2: One of Main System Fluids– Generation of Thermodynamic Property Tables outside the Code – New Search Routines for Thermodynamic Property Tables– State-of-the-Art Transport Properties in Functional Form
Verification and Validation
ReasonableModeling capability of complicated fluid systems (IHX Problem)
Multi-Fluid System
ReasonablePropagation of inlet flow and temperature perturbation
2-D Slab Transients
Good Agreement with ATHENA
Cooldown & heatup transients at 1-φ/2-φ/supercritical states
1-D Transients
Good Agreement with NIST
Accuracy of calculated properties at 1-φ/2-φ/supercritical states
1-D Steady States
ResultsObjectivesProblem ID
-17/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Convection Heat Transfer Model
Original MARS Heat Transfer Models– Forced Turbulent Convection Heat Transfer
• Dittus-Boelter Model – Heat Transfer at Low Reynolds Number
• Maximum of Free Convection, Laminar and Forced Turbulent
Technical Issues– Dittus-Boelter Forced Convection Model is known to Over-
predict– Wall Temperature and Geometric Effects become more
Dominant in Gas Flows– Heat Transfer Regimes during Conduction Cooling Transients
are in Free, Mixed, Laminar or Turbulent Convections
-18/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Churchill-ChuNatural
Burmeister (Gr < Re2)TransitionCriterion
ChurchillMinimum (hlam, htur)ChurchillMixed
Aicher (Ra1/3/(Re0.8Pr0.4) < 0.05 )TransitionCriterion
Olson
Interpolation between hlam and htur (2300 <
Re < 5000)
Nu = 4.364 (heating)
Nu = 3.657 (cooling)
Forced
TurbulentTransitionLaminarRegime
Gas Heat Transfer Regime Map
MIT Model based on Metais-Eckert MapHeat Transfer Regime during GFR Post-LOCA Decay Heat Removal
-19/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Assessment: Turbulent Forced Convection Model
1067.1027.1042.1048.Reynolds No. in Core28.~41.38.5~42.638.5~42.638.~40.2HTC in Core
Gniel. (’75) w/o Twall EffectGniel (‘75)Gniel.
(’75)Olson (’00)
21.~36.40.3~65.040.3~65.138.2~55.1HTC in HX
1067.01027.01026.31047.9Max. Clad. Temp.951.0935.4934.9948.7Temp. at Core Outlet440.0429.8429.7441.4Temp. at Core Inlet8.748.908.918.82Loop Flow
LOCA-COLAATHENAMARS-GCRCalculated Variables
Units in SI (bar, kg/s, K, W/m2-K)
Gas Heat Transfer Regime Map
-20/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
0 5 10 15 20 25
0
10
20
30
40
50
60
LOCA-COLA MARS
Dec
ay H
eat R
emov
ed (M
W)
Pressure (bar)
Comparison of GFR Decay Heat Removal CapabilityComparison of GFR Decay Heat Removal Capability
Assessment: Whole Heat Transfer Package- GFR Decay Heat Removal Capability compared with LOCA-COLA (MIT)
Gas Heat Transfer Regime Map
-21/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Contact Heat Transfer
Contact Heat Transfer Model– Need to model the Heat Conduction by “Contact” between
Fuel Pebbles, Blocks, and Vessel Internals– Simple Model as a Short-Term Resolution
Qcon = Acon Hcon (Ti-Tj) = Ai (Acon/Ai) Hcon (Ti-Tj)= Ai Heff (Ti-Tj)
where Heff is the Effective Thermal ConductivityCurrently, Constant Input Value is provided by User.Mechanistic Model will be developed.
– Verified on Debugger Level
-22/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Multi-D Hydrodynamic Component
Geometry– Rectangular: Slab– Cylindrical: Downcomer, Core, Pipe, Tank
3-D, 2-Phase Flow Formulation– Porous Media Approach:
• Volume (γv) and Area Fraction (γs)– 3-D Momentum Equation
– 3-D Energy Equation
– 3-D Flow Regime Map• Modified Flow Regime Map based on 1-D Map
y
x
γs,x A
γs,y A
αfγv V
αgγv VV
( ) ( ) wiskv
kkkkkkksv
kkk FFgPvvvt
−−∇+=⋅∇+∇+∂∂ τγα
γρααραγ
γρα 11
( ) ( )[ ]kkUkkkvkkkv vUKV
VU
tραγραγ ⋅∇⎟
⎠⎞
⎜⎝⎛+
∂∂ 1( ) ( )[ ]kk
Ukkkvkkkv vUKV
VU
tραγραγ ⋅∇⎟
⎠⎞
⎜⎝⎛+
∂∂ 1 ( )⎥
⎦
⎤⎢⎣
⎡ ⋅∇⎟⎠⎞
⎜⎝⎛+
∂∂−= kkv
kVk vV
VtP αγαγ 1 ( )⎥
⎦
⎤⎢⎣
⎡ ⋅∇⎟⎠⎞
⎜⎝⎛+
∂∂−= kkv
kVk vV
VtP αγαγ 1 ( ) [ ]
kkvkkskvk qVV
PU '1/ αγργ ⋅∇⎟⎠⎞
⎜⎝⎛−+Γ+ ( ) [ ]
kkvkkskvk qVV
PU '1/ αγργ ⋅∇⎟⎠⎞
⎜⎝⎛−+Γ+
-23/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
RPI Air-Water Test
10 20 30 40 50 60 70 800.00.10.20.30.40.50.60.70.80.91.0
10 20 30 40 50 60 70 800.00.10.20.30.40.50.60.70.80.91.0
10 20 30 40 50 60 70 800.00.10.20.30.40.50.60.70.80.91.0
Void
Fra
ctio
n
Lateral position (cm)
Lower Position
Air-Water outlet Water inlet
Air-Water outlet
Air-Water Inlet
Middle Position
Top Position
Experiment Modified MARS
1-Φ WaterInlet
2-Φ WaterAir Outlet
2-Φ WaterAir Outlet
2-Φ WaterAir Inlet
Air Velocity
Void Fraction
Calculated Void Distribution
V&V of Multi-D Hydrodynamic Component
-24/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
HPCC Event Analysis using MARS-GCR
Reference Plants– NGNP 600 MWth PMR (Thot = 1000oC)– NGNP 300 MWth PBR (Thot = 1000oC)– GT-MHR Air-Cooled RCCS
MARS Modeling10
7
6
5
4
3
2
Out In
3 core ring
Centerreflector
Outerreflector
Coolant channel
Bypassregion
Outer reflecto
r
Center reflecto
r
PMR600 (1-D) PBR300 (Multi-D) GT-MHR RCCS (Multi-D)
Coolantriser
Core
ReflectorBypass112
Outlet pipe
Outlet Inlet
130 : Upper plenum
110 : Core
Cen
ter reflector
Outer reflecto
r
Vessel w
all
Coolantriser
Core
ReflectorBypass
Coolantriser
Core
ReflectorBypass112
Outlet pipe
Outlet Inlet
130 : Upper plenum
110 : Core
Cen
ter reflector
Outer reflecto
r
Vessel w
all
900 Reactor Cavity(Multi-D Component, 2-r, 1-θ, 15-z)
970
Riser
960
Down-comer
965Flow distributer
975
980
955
950
Concrete Soil
900 Reactor Cavity(Multi-D Component, 2-r, 1-θ, 15-z)
970
Riser
960
Down-comer
965Flow distributer
975
980
955
950
Concrete Soil
130(Riser
&Head)
140 (Upper plenum)
160 (Lower plenum)110(Inlet ann.)
120 (SCS & Lower head)
100(Inlet)
170(Outlet)
145
OuterReflecor
156
OuterCore
154
MiddleCore
152
InnerCore
142
InnerReflecor
-25/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Multi-Group Cross Section TreatmentCross Section Functionalization for Gas-Cooled Reactors – Burnup– Moderator Temperature– Fuel Temperature:
Radial Reflector Treatment
Axial Block Shuffling Scheme (to be developed)
Thermal-Hydraulic Feedback Model for GCR (to be developed)
Improvement of MASTER for GCR Applications
mm
ff
mfmf T∆TσT∆
Tσ),TT(Bσ),TT(Bσ
∂∂
∂∂ ++= 00,,
-26/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Code Flow Chart of MASTER
Lattice Calculation
Physics Analysis
XS Functionalization
WIMSD4 Library
DRAGON
Output
PROLOG
MASTER
XS Tableset
LIBERTE/HELIOS
Library
Output
DOPS Output ProcessingHOPE
HGC File
-27/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
Result of Benchmark Calculation
0.910.95-.04
0.990.970.02
0.840.87-.03
1.191.190.00
1.021.000.02
1.101.100.00
1.081.050.03
0.940.940.00
0.970.99-.02
1.071.050.02
1.021.000.02
0.950.96-.01
1.191.180.01
0.990.970.02
0.810.85-.04
0.981.00-.02
0.960.97-.01
Keff: - MCNP : 1.39189- MASTER : 1.39366
- MCNP- HELIOS/MASTER- Difference
Prismatic NGNP (INL) Reactor Core
-28/28-KAERIKAERI-- Nuclear Hydrogen Development & Demonstration ProjectNuclear Hydrogen Development & Demonstration Project
MARS/MASTER for GCR will be ready in a few months.
MARS/MASTER-GCR