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Advanced Methods for BWR Transient and Stability Analysis by elfphabet5

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									      Advanced Methods for
BWR Transient and Stability Analysis



                         F. Wehle, S. Opel, R. Velten
                              Framatome ANP GmbH
                                      P.O. BOX 3220
                            91050 Erlangen Germany
                     Advanced Methods for BWR
                   Transient and Stability Analysis

    > Background and Overview of Framatome ANP’s
       BWR Methodology


    > Application of the Advanced Transient Analysis

    > OECD/NRC Boiling Water Reactor Turbine Trip
       Benchmark


    > KATHY-Loop Stability Measurements

    KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
2   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
    Challenges for Design and Operation of
    Modern BWR Fuel Assemblies and Cores


     >Customer                                                    Optimal fuel utilization for safe, reliable
                                                                  and highly flexible reactor operation



    > Framatome ANP                                             l   Advanced fuel design
                                                                l   Modern core loading concepts
                                                                l   High operational flexibility

    > Design Tools                                              l   Comprehensive physical modelling
                                                                l   Qualified single codes and code
                                                                    systems



     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
3    Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
           Overview of Framatome ANP’s BWR
                     Methodology


         MCNP                     CASMO-4                                THRP             RINGS               CARO
      Monte-Carlo              Neutronics Lattice                2-Phase Thermal         Subchannel          Thermo-
                                                                    Hydraulics            Analysis          Mechanical
                                                               Fuel Assembly

                MICROBURN-B2                                        PRIMO-B             POWERPLEX/FNR-K
                       Core Simulator                             Loading Pattern        Online Core Monitoring
                                                                    Optimization
                                                            3D Core Steady State

                         RAMONA-3                                   COBRA-TF                    STAIF
                         3D-Space-Time                        Transient Subchannel        Stability in Frequency
                            Kinetics                           Thermal Hydraulics                 Domain

                                                                 Core Transients

                              VERENA(RELCOS)/COSBWR/FRANCESCA
                                                                  Plant Analysis

                                                               Plant Transients

    KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
4   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
           Overview of Framatome ANP’s BWR
                     Methodology


         MCNP                     CASMO-4                                THRP              RINGS               CARO
      Monte-Carlo              Neutronics Lattice                2-Phase Thermal          Subchannel          Thermo-
                                                                    Hydraulics             Analysis          Mechanical
                                                               Fuel Assembly

                MICROBURN-B2                                        PRIMO-B             POWERPLEX/FNR-K
                      Core Simulator                            Loading Pattern          Online Core Monitoring
                                                                  Optimization
                                                            3D Core Steady State

                         RAMONA-5                                   COBRA-TF                     STAIF
                         3D-Space-Time                        Transient Subchannel         Stability in Frequency
                            Kinetics                           Thermal Hydraulics                  Domain

                                                                 Core Transients

                                                      S-RELAP/RAMONA-5
                                 Best Estimate Plant Analysis, 3D Core Representation

                                                               Plant Transients

    KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
5   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                        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)




      KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
6     Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
           RAMONA – Hydraulic Model Components

                                     Steam Dome
                                                                                                   MSIV            Turbine-Valve



                                                   Steam Separator
                                                                                      S/R-Valves          Bypass

    Feedwater                                         Stand Pipes

                Downcomer 1                          Upper Plenum




                                                                             Bypass
                                                        Core
                                                    Parallel Channels




                Downcomer 2




                                                    Lower Plenum 2




                                   Lower Plenum 1




        KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
7       Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
               BOC - Core Averaged Axial Power




    KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
8   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                          BOC – Radial Power Factors




    KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
9   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                EOC - Core Averaged Axial Power




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
10   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
               Comparison of the Fission Powers




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
11   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
     Limiting Case – Radial Factor of Hot & Cold Channel




       KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
12     Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
     Limiting Case – MCPR of the Hot Channel




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
13   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                          BWR Turbine Trip Benchmark


     > Exercise 1
       n Power vs. Time plant system simulation with fixed axial power profile
            table is given => thermal-hydraulic system response
     > Exercise 2
       n Coupled 3D and/or 1D kinetics/core thermal-hydraulic BC model
            l      Hot zero power.
            l      Hot full power and transient using the provided core BC.

     > Exercise 3
       n Best-estimate coupled 3D core/thermal-hydraulic system modeling




       KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
14     Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                                           Plant Code S-RELAP5


     > S-RELAP5 is based on RELAP5/MOD2 and incorporates
       elements 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



        KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
15      Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                                   Exercise 3: Fission Rate




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
16   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                              Exercise 3: Dome Pressure




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
17   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
         Advanced Transient Methodology - Summary



     > Advanced method reduces OLMCPR by app. 0.07
      compared to the conservative 1D methodology
     > The method allows more operational flexibility.
     > The advanced transient method has already been
      approved by TÜV NORD.
     > Based on the OECD/NRC BWR Turbine Trip
      Benchmark the transient applicability of the code
      system S-RELAP5/RAMONA5 has been proven
      successfully.


       KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
18     Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
     Feedback Mechanisms of BWR Stability


                                               Exit Flow Rate                                     Neutronics Feedback

                                                                                                                Heat Flux


                                                                                                             Rod Temperature
              Thermal Hydraulics                         δ∆ p
                                                                II
              (Core and External Loop)
                                                                                                              Thermal Power
                       δ∆ p        = - δ∆p
                                                          δα                             Void Fraction
                              II          I                                                  δα
                                                                                                               Neutron Flux



                                                          δ∆p                                                   Reactivity
                                                             I

                                                                                                              Void Reactivity
                                                                                                                Coefficient

                                               Inlet Flow Rate




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
19   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
             Most Sensitive Stability Parameters



                   Fuel Assembly Parameters                                                   Effect on Stability
                   Flow Area                                                                          +
                   Hydraulic Diameter                                                                 +
                   Loss Coefficient LTP                                                               +
                   Loss Coefficient UTP                                                                -
                   Loss Coefficient Spacer                                                             -
                   Fuel Time Constant                                                                 +
                   Void Coefficient                                                                   +

                   Operating Parameters
                   Axial Peaking Factor                                                               -
                   Radial Peaking Factor                                                              -
                   Reactor Power                                                                      -
                   Reactor Mass Flow                                                                  +
                   Inlet Subcooling                                                                   -


     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
20   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
     Multifunction Thermal Hydraulic Test Loop
                      KATHY
                                                                                                                        Pressurizer

                                                                       Direct contact
                                                                       condenser




                                                                                                          Water steam            To
                                                                                                          seperator              con-
                                                                                                                                 enser

                                          High pressure     5 MW
                                          coolers
                                                                                                    Circulation
                                                                                                    pump

                                                                   10 MW
                                                                           Void Fraction                                         Feed
                                                                           Measurement                                           water
                                                                           Device
                                                                                                             Control
                                                                                Pel. ≤ 15 MW                 valve

                                                                                                 BWR
                                                                                                 Test Vessel
                                                                                                                               Control
                                                   PWR                                           p ≤ 110 bar                   valve
                                Pel.               Test Vessel
                                ≤ 9,5MW            p ≤ 185 bar
                                                                                                                           Downcomer




                                                                                               Natural Circulation
                                                                                               Loop




      KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
21    Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                           KATHY Stability Test Loop

                                                                             Steam Separator + Expansion Chamber



                       Riser
                                                                                  Downcomer
                            ζexit
                            ζspacer

                            ζspacer

                            ζspacer

                            ζspacer                        Test
                                                          Section
                            ζspacer

                            ζspacer

                            ζspacer


                            ζinlet                                                   0.            1.0          1.6
                                                                                          Axial Power Profile


     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
22   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                                         Steady State Flow Rate


                                           ζexit= 1.5
     Flow Rate                                                              DR = 1
       (kg/s)
                                                                                             CPR = 1
                                                        DR = 1



                                                                                   CPR = 1

                                                      ζexit= 7.5




                                                                   Inlet Subcooling: 124 kJ/kg
                                                                   Inlet Subcooling: 144 kJ/kg



                                                                     Bundle Power (MW)

         KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
23       Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                                KATHY Stability Test Data




                                                                                    DR: 0.77




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
24   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
               Transient Dryout During Instability




     KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
25   Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
     Comparison of STAIF Results with Karlstein
                  Stability Tests




       KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
26    Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                             Transient Dryout Tests Simulating
                                Typical Limiting Transients
                                                                                                       1.4


                                                                                                       1.2




                                                                                 Standardized values
                                                                                                       1.0
                                                                                                                                                                   Power
                                                                                                                                                                   System pressure
                                                                                                                                                                   Massflow
                                                                                                       0.8
                     System data during turbine trip
                                                                                                       0.6


                                                                                                       0.4


                                                                                                       0.2


                                                                                                       0.0
                                                                                                             0   1   2   3   4   5   6   7   8   9   10 11 12 13 14 15 16 17 18 19 20
                                                                                                                                                     Time
                   350

                   340

                   330

                   320
     Temperature




                   310

                   300

                   290                                                                                                               Rod temperature response during
                   280
                                                                                                                                     turbine trip
                   270

                   260

                   250
                         0   1   2   3   4   5   6   7   8   9    10 11 12 13 14 15 16 17 18 19 20
                                                                 Time
             KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
27          Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP
                                                            Conclusions
     > Safe, reliable, and flexible BWR operation requires fuel
       assembly and core designs optimized for all reactor operating
       conditions.
     > The comprehensive methodology of Framatome ANP meets the
       challenges to analyze and predict steady-state and transient
       BWR operation.

     - The methodology is based on state-of-the-art
       physical modeling.
     - It has been thoroughly qualified, using a large
       database including recent, sophisticated, and highly
       accurate measurements.
     - The code system is further developed and qualified
       continuously.

        KTG-Fachtagung „Reaktorbetrieb und Kernüberwachung“, 13.-14. Febr. 2003, FZ-Rossendorf
28     Advanced Methods for BWR Transient and Stability Analysis, F.Wehle, Framatome ANP

								
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