wir schaffen wissen – heute für morgen a. dehbi, d. suckow, t. lind, s. guentay paul scherrer...
TRANSCRIPT
Wir schaffen Wissen – heute für morgen
A. Dehbi, D. Suckow, T. Lind, S. GuentayPaul Scherrer Institut, Switzerland
Large Scale Experimental Program at PSI on Safety Issues in a PWR Steam Generator
ERMSAR2012, Cologne, Germany, March 21-23, 2012
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 2
Project Overview – International collaboration project Steam condensation / Reflux condensation
• Background• Objectives of the Reflux Project• Reflux Single Tube Test Facility• Reflux Test Plan
Steam Generator Mixing and Recirculation under SBO initiated Severe Accident Conditions
• Background• System code approach• CFD Simulation• Facility Scaling• Test Facility and Experimental Program
Summary
Presentation Outline
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 3
1) Steam / Reflux condensation, DBA and BDBA: Amount of coolant available for core cooling Timing and efficiency of EOP and SAM measures• To Improve system codes and bench-mark CFD
- In the presence of non-condensable gases- In the presence of aerosols- At high pressures (20 -100 bar)
2) Mixing and recirculation in the steam generator during PWR severe accidents:
Thermal challenge to primary pressure boundary Failure of the components Source term• To scale-up of the methodology and bench-mark CFD• 1/7 scale facility with improved scaling and instrumentation• The effect of the steam generator design (geometry)
Two Part Project Overview
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 4
Reflux condensation: Background (1)
o Reflux condensation removes residual decay heat under conditions with:• reduced primary side water inventory• secondary side heat sink• LOCA, mid-loop operation
o Condensate flows counter-current to steam• Steam generated due to decay heat• Condensation in the steam generator• Condensate flows back into core• Different modes of operation: film-wise,
oscillatory, carry-overFrom RV
To RV
U
Xg
T
Wall
Condensate Mixture of Steam,NC-Gas
Hot Leg
SG Tubes
SG secondary side
Outlet Plenum
Inlet Plenum Condensate
Mixture of Steam,NC-Gas
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 5
• Pure steam condenses efficiently• Efficiency decreased by:
• Non-condensable (NC) gases - N2 from accumulator injection- Air migration during mid-loop operation- H2 from fuel (severe accident)• Aerosols (severe accident)
Heat transfer and steam condensation during counter / co-current flow• at high pressures (5-100bar)• for high content of non-condensable gases N2
and He (H2)• under co-current and counter current flow
conditions => CCFL• in laminar to turbulent flow regimes• in the presence of aerosols
Reflux condensation: Objectives
Aerosol deposition
super-heated steam and NC gas
Aerosols
Condensation under influences of NC gasand aerosols
Degrading
Boiling cross over leg(loop seal)
cold leg
hot leg
surg
e lin
e
Pre
ssur
izer
SG outletplenum
SG inletplenum
SG secondary side
U-tube bundle
Steam Generator SG
Reactorvessel
Hot legbend
Aerosol deposition
super-heated steam and NC gas
Aerosols
Condensation under influences of NC gasand aerosols
Degrading
Boiling cross over leg(loop seal)
cold leg
hot leg
surg
e lin
e
Pre
ssur
izer
SG outletplenum
SG inletplenum
SG secondary side
U-tube bundle
Steam Generator SG
Reactorvessel
Hot legbend
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 6
TRACE Condensation Model: Status*
*A. Manera, CAMP Meeting, Nov. 2007
Film Condensation without NC Gases•Very good agreement for condensation without NC for large pressure range•Improvements needed for very low pressure and low liquid film Reynolds numbers
Film Condensation with NC Gases•Default model of TRACE code very approximate•Significant improvements with TRACE advanced condensation model•Further developments still needed for:•High content of NC (20-90%)•High pressures (20-100 bar)
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 7
RFLX Single Tube Facility
Tube 1: 45 x 20 mm Tube 2: 19.05 x 16.8 mm Length 4.5 m Material SS 316L
Steam: up to 25 kg/h NC: N2 0-91 w-%
He: 0-45 w-%
Primary: 1.5 -100 bar 400°C Secondary: 1 - 80 bar 35 – 295°C
saturatedor subcooledwater cooling
MM
He
N2
SteamGenerator
SuperHeater
Mixer
Heater
HX
Flowrate
Condensate
HXM
M
M
CondensateSeparator
Non-Condensables
dem.Water
SeparatorDrum
Condenser/Pressurizer
PrimaryLoop
HeaterCirculationPump
SecondaryLoop
4.5
m
el.
HX
Heater
FlowRate
SprayPump
upperplenum
lowerplenum
M
HX
Flowrate
Flowrate
Flowrate
ø 45 x 20
ø 114.3
(ø 19.05 x 16.8)
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 8
RFLX Test matrix
Test matrix comprised of 5 Phases and 50 Tests
Configuration Characteristics, Variations
I Reflux mode, pure steam condensation NC mass fraction: 0%Primary total pressure: 2 - 95 barInjection from bottom / top
II Reflux mode, steam + noncondensable (NC) NC mass fraction: 1% - 91%Primary total pressure: 2 - 95 bar
III Once-through counter-current mode (NC) NC mass fraction: 1% - 91% Primary total pressure: 2 - 95 barup to CCFL point
IV Once-through co-current mode NC mass fraction: 1% – 91%Primary total pressure: 2 - 95 barCCFL onwards to flooding, spill-over
V Open tests To be assigned
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 9
Steam Generator Mixing: Background
o SBO severe accident sequence• Hot leg voided by venting coolant through
pressurizer• Cold leg loop seal plugged with water• Primary: high pressure; Secondary: dry,
depressurized (“high, dry, low”)o Hotleg counter-current natural circulation
• Transfer heat to hot leg, surge line and SG tubes• Hot flow counter-current to cold flow• Mixing of hot and cold gas in inlet plenum• Flow recirculation through SG U-tubes Thermal challenge to surge line and SG tubes Source term
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 10
Mixing: System Code Approach
o MELCOR 1.8.5: Pairs of flow paths to simulate counter-current and inlet plenum mixing
o Required inputs:• Recirculation ratio: flow rate in tubes/flow rate in hotleg
• Fraction of tubes which receive hot fluid (flow upwards)
→ To predict the actual response and mixing parameters requires experimentally validated CFD
o SOARCA by US NRC (NUREG-1935, 2012):• Limited data available, only average behaviour• Dependence on geometry, data available for only
one geometry => validity for other geometries?
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 11
Facility Scaling: Dimensionless Numbers
360
600
7400
35500
PSI
270
670
8200
170000
PWR
350
210
9200
46500
WG 1/7Parameter
360
600
7400
35500
PSI
270
670
8200
170000
PWR
350
210
9200
46500
WG 1/7Parameter
h
eqHLhHL
DU
Re
otubes
tubestube A
Hm
Re
2Retube
tubetube
GrRi
2
__ ReHL
BundleSGBundleSGHL
GrRi
o Westinghouse (1990) tests to experimentally investigate natural circulation flows during severe accidents in PWRs; limitations on data application: scaling (not conservative), data proprietary
Improved scaling: increased height and number of tubes, reduced tube diameter increased resistance increased Ritube
Improved instrumentation
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 12
Schematic of the SG Mixing Facility
Program will produce CFD-grade data: high spatial / temporal resolution of flow fieldo PIV (2 components of velocity and RMS)o Two component LDA:
• Velocity profiles (mean & RMS)• Reynolds stresses, thermal stresses
o Thermocouples (tubes), and thermocouple meshes (hot leg, inlet / outlet plenum)
RPV
Hot leg
Steamgenerator
Leakageexpansion
volumeC
ompr
esso
r
HeatingHeating
SecondaryAir cooling
Surgeline
Parameter Value
Hot leg length (m) 1.2
Hot leg diameter (mm) 83.7
Number of U-tubes 262
Inner Diameter of tubes (mm) 5.0
Tube height (straight) (m) 2.2
SG bundle radius (m) 0.235
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 13
Experimental Program
1. Base case: circulation and mixing under “high-dry-low” scenario2. Effect of light gas: He
• Concern: presence of light gas, under low driving ΔT, could lead to stratification and impairment/disruption of counter-current flow (no data available)
3. Leakage: effect of tube leakage on mixing• Leakage will progressively disrupt counter-current flow no data available on the
dynamics of this effect4. Geometry of inlet plenum
• CFD indicates large variations in recirculation ratio no experimental data available with different inlet plenum geometries
NPP Mixing factorFraction hot
tubes
West. 2.7 50 %
CE 1.5 42 %
Boyd: Geometry effect, base case
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 14
Summary
The Reflux tests will:• Extend available data base to improve system codes and bench-mark CFD
• In the presence of non-condensable gases• In the presence of aerosols• At high pressures (20-100 bar)
Amount of coolant available for core cooling Better evaluation of accident prgress Timing and efficiency of EOP and SAM measures
The Mixing tests will:• Provide critical mixing parameters (not constant )
• Improved scaling• Effect of different geometries• Light gas• Effect of tube breach
Help protect pressure boundary by better informed accident management Better assessment of the source term
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 15
Thank you for your attention
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 16
RFLX Facility, Measurements
• Local heat flux → set of thermocouples→ thin-foil heat flux sensors
• Condensate film → flush-mounted pin and wire-wire electrode conductance probes• Condensate flow → Coriolis mass flow meters• Pressure → differential pressure transducers
t
Tw
To
Ti
Tc
Thin-FoilHeat FluxSensor
ThermocouplesHeat FluxMeasurement
Tb
Conductance Pin Electrodes
Condensate FilmMeasurement
Parallel WireConductance Probe
Nuclear Energy and SafetyLaboratory for Thermal Hydraulics
Severe Accident Research Group, SACRE
ERMSAR2012, March 21-22, 2012 PSI, 21.04.23, 17
CFD Simulations of Mixing
o At NRC, C. Boyd: 1/7 Westinghouse and full-scale• “A challenge … the extension of a limited set of available test data at 1/7th
scale to the full scale conditions”o At PSI, A. Dehbi: 1/7 Westinghouse
• Flow turbulent and erratic, hot plume wanders around High resolution temporal and spatial data required to benchmark codes
MeanInstan. t=1190 s Instan. t=1210 s