advanced methods for bwr transient and stability …...transient subchannel thermal hydraulics 3d...
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Advanced Methods forBWR Transient and Stability Analysis
F. Wehle, S. Opel, R. VeltenFramatome ANP GmbH
P.O. BOX 322091050 Erlangen Germany
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP2
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Advanced Methods for BWRTransient and Stability Analysis
> Background and Overview of Framatome ANP’s
BWR Methodology
> Application of the Advanced Transient Analysis
> OECD/NRC Boiling Water Reactor Turbine TripBenchmark
> KATHY-Loop Stability Measurements
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP3
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Challenges for Design and Operation ofModern BWR Fuel Assemblies and Cores
> Framatome ANP � Advanced fuel design� Modern core loading concepts� High operational flexibility
> Design Tools � Comprehensive physical modelling� Qualified single codes and code
systems
>Customer Optimal fuel utilization for safe, reliableand highly flexible reactor operation
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP4
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Overview of Framatome ANP’s BWRMethodology
Fuel Assembly
Plant Transients
Core Transients
CASMO-4Neutronics Lattice
THRP2-Phase Thermal
Hydraulics
CAROThermo-
Mechanical
MCNPMonte-Carlo
RINGSSubchannel
Analysis
MICROBURN-B2Core Simulator
POWERPLEX/FNR-KOnline Core Monitoring
PRIMO-BLoading Pattern
Optimization
STAIFStability in Frequency
Domain
RAMONA-33D-Space-Time
Kinetics
VERENA(RELCOS)/COSBWR/FRANCESCAPlant Analysis
COBRA-TFTransient Subchannel
Thermal Hydraulics
3D Core Steady State
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP5
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Overview of Framatome ANP’s BWRMethodology
Fuel Assembly
Plant Transients
Core Transients
CASMO-4Neutronics Lattice
THRP2-Phase Thermal
Hydraulics
CAROThermo-
Mechanical
MCNPMonte-Carlo
RINGSSubchannel
Analysis
MICROBURN-B2Core Simulator
POWERPLEX/FNR-KOnline Core Monitoring
PRIMO-BLoading Pattern
Optimization
STAIFStability in Frequency
Domain
RAMONA-53D-Space-Time
Kinetics
S-RELAP/RAMONA-5Best Estimate Plant Analysis, 3D Core Representation
COBRA-TFTransient Subchannel
Thermal Hydraulics
3D Core Steady State
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP6
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
3D Transient Code RAMONA 3
- Neutronics: 11/2-Group Diffusion Model
- Thermal Hydraulics: 4-Equation Drift Flux Model
- BWR System Components: Pumps, Separators, Steam Line,Reactor Protection System
Validation:- Peach Bottom Turbine Trip- Spert Reactivity Insertion Experiments- Ringhals Stability Benchmark- Validation against Plant Stability Measurements and Operational Transients- GUN C Cycle 12 and 13 (global and regional instabilities)
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP7
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
RAMONA – Hydraulic Model Components
Lower Plenum 1
Steam Separator
Stand Pipes
Upper Plenum
Byp
ass
Lower Plenum 2
Steam Dome
Downcomer 1
Downcomer 2
Parallel Channels
Core
Feedwater
S/R-Valves
MSIV
Bypass
Turbine-Valve
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP8
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
BOC - Core Averaged Axial Power
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP9
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
BOC – Radial Power Factors
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP10
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
EOC - Core Averaged Axial Power
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP11
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Comparison of the Fission Powers
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP12
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Limiting Case – Radial Factor of Hot & Cold Channel
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP13
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Limiting Case – MCPR of the Hot Channel
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP14
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
BWR Turbine Trip Benchmark
> Exercise 1
� Power vs. Time plant system simulation with fixed axial power profile
table is given => thermal-hydraulic system response
> Exercise 2
� Coupled 3D and/or 1D kinetics/core thermal-hydraulic BC model
� Hot zero power.
� Hot full power and transient using the provided core BC.
> Exercise 3
� Best-estimate coupled 3D core/thermal-hydraulic system modeling
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP15
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Plant Code S-RELAP5
> S-RELAP5 is based on RELAP5/MOD2 and incorporateselements of RELAP5/MOD3 and RELAP5-3D
> Special Features:
- 2-dimensional component model
- improved formulations for energy and momentum equations
- modified heat transfer and hydrodynamic constitutive models
- special fuel modeling
- suited for best-estimate licensing methods
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP16
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Exercise 3: Fission Rate
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP17
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Exercise 3: Dome Pressure
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP18
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Advanced Transient Methodology - Summary
> Advanced method reduces OLMCPR by app. 0.07compared to the conservative 1D methodology
> The method allows more operational flexibility.
> The advanced transient method has already beenapproved by TÜV NORD.
> Based on the OECD/NRC BWR Turbine TripBenchmark the transient applicability of the codesystem S-RELAP5/RAMONA5 has been provensuccessfully.
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP19
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Heat Flux
Rod Temperature
Thermal Power
Neutron Flux
Reactivity
Void ReactivityCoefficient
Void Fractionδαδαδαδα
δαδαδαδα
δ∆δ∆δ∆δ∆pI
δ∆δ∆δ∆δ∆ pII
Inlet Flow Rate
Exit Flow Rate
Thermal Hydraulics
(Core and External Loop)
Neutronics Feedback
δ∆δ∆δ∆δ∆ pII
= - δ∆δ∆δ∆δ∆pI
Feedback Mechanisms of BWR Stability
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP20
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Most Sensitive Stability Parameters
Fuel Assembly Parameters Effect on StabilityFlow Area +Hydraulic Diameter +Loss Coefficient LTP +Loss Coefficient UTP -Loss Coefficient Spacer -Fuel Time Constant +Void Coefficient +
Operating ParametersAxial Peaking Factor -Radial Peaking Factor -Reactor Power -Reactor Mass Flow +Inlet Subcooling -
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP21
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Multifunction Thermal Hydraulic Test LoopKATHY
Direct contactcondenser
P≤ 9,5MW
el.
Pressurizer
Natural CirculationLoop
Controlvalve
Controlvalve
Void FractionMeasurementDevice
P ≤ 15 MWel.
Downcomer
Water steamseperator
Circulationpump
PWRTest Vessel
10 MW
5MWHigh pressurecoolers
p ≤ 185 bar
p ≤ 110 bar
BWRTest Vessel
Feedwater
Tocon-enser
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP22
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
KATHY Stability Test Loop
ζζζζinlet
ζζζζexit
ζζζζspacer
ζζζζspacer
ζζζζspacer
ζζζζspacer
ζζζζspacer
ζζζζspacer
ζζζζspacer
Axial Power Profile
Downcomer
Steam Separator + Expansion Chamber
TestSection
1.0 1.60.
Riser
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP23
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Steady State Flow Rate
Bundle Power (MW)
Flow Rate
ζζζζexit= 7.5
Inlet Subcooling: 124 kJ/kg
Inlet Subcooling: 144 kJ/kg
CPR = 1
CPR = 1
DR = 1
DR = 1
(kg/s)
ζζζζexit= 1.5
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP24
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
KATHY Stability Test Data
DR: 0.77
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP25
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Transient Dryout During Instability
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP26
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Comparison of STAIF Results with KarlsteinStability Tests
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP27
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Transient Dryout Tests SimulatingTypical Limiting Transients
0.0
0.2
0.4
0.6
0.8
1.0
1.2
1.4
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20
Time
Sta
nd
ard
ized
valu
es
PowerSystem pressureMassflow
250
260
270
280
290
300
310
320
330
340
350
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20
Time
Tem
per
atu
re
System data during turbine trip
Rod temperature response duringturbine trip
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Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP28
KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
Conclusions
> Safe, reliable, and flexible BWR operation requires fuelassembly and core designs optimized for all reactor operatingconditions.
> The comprehensive methodology of Framatome ANP meets thechallenges to analyze and predict steady-state and transientBWR operation.
- The methodology is based on state-of-the-artphysical modeling.
- It has been thoroughly qualified, using a largedatabase including recent, sophisticated, and highlyaccurate measurements.
- The code system is further developed and qualifiedcontinuously.