Advanced Methods for BWR Transient and Stability …...Transient Subchannel Thermal Hydraulics 3D Core Steady State 6 Advanced Methods for BWR Transient and Stability Analysis, F.Wehle,
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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
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
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
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
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
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)
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
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
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
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
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
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
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
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
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
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
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
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.
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
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 -
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
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
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
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
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
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
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
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.
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