pb-bi cooled direct contact boiling water small reactor...by mext (fy2002-2004) pb-bi cooled direct...
TRANSCRIPT
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by M. Takahashi1, S. Uchida2, K. Hata3, T. Matsuzawa2, H. Osada2, Y. Kasahara2, Y. Yamada2, N. Sawa2, Y. Okubo2, K. Koyama2,
M. Hirabayashi4, K. Ara4, T. Obara1, and E. Yusibani51Tokyo Institute of Technology (Tokyo Tech.)
2Advanced Reactor Technology Co., Ltd. (ARTECH)3Nuclear Development Corporation (NDC)
4Japan Nuclear Cycle Development Institute (JNC)
PbPb--Bi Cooled Direct Contact Boiling Bi Cooled Direct Contact Boiling Water Small ReactorWater Small Reactor
INES-1, Tokyo, Japan, November 1-4, 2004,
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1. Energy park and small reactor2. Motivation3. Project4. Conceptual design of PBWFR 5. Lift pump in chimney6. Removal of Pb-Bi mists and polonium7. Concluding remarks
ContentsContents
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Stable FP
Energy Park
Natural U or Th
Actinide
Long Life FP
FPPb, Bi
(Option)
(Leak)
Transmutation StorageSeparation
FP:Fission Products
Energy UtilizationWith Small Reactor
Outside of Park
Toxic sub.IN
Toxic sub.OUT
Energy Park and Small Reactors with Long Life
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Long Life Small PFRLong Life Small PFR- Forced Convection- Gas Lift Pump
SelfSelf--controllable controllable NaNa--cooled Small FRcooled Small FR
HTGRHTGR(CANDLE Burning)
COCO22 Gas TurbineGas TurbineReactorReactor(HighEfficiency, LMFR)
Large PFR-Transmutation-CANDLE Burning
Self-controllable Na-cooled Large FR
Nuclear Energy Park
Outside of Park (Site)Production of Electricity, Heat and Hydrogen
CO2 Gas TurbineMedium Size Reactor
Transportationof Reactors
Long Life Small PFRLong Life Small LFR- Forced Convection- Gas Lift Pump
SelfSelf--controllable controllable NaNa--cooled Small FRcooled Small FR
HTGRHTGR(CANDLE Burning)
COCO22 Gas TurbineGas TurbineReactorReactor(HighEfficiency, LMFR)
Large LFR-Transmutation-CANDLE Burning
Self-controllable Na-cooled Large FR
Nuclear Energy Park
Outside of Park (Site)Production of Electricity, Heat and Hydrogen
CO2 Gas TurbineMedium Size Reactor
Transportationof Reactors
Reactors in Park and Sites
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Safe Coolant: Inactive with air, water Void reactivity: Negative
Economic Simple or Reduction of material e. g., Elimination of
- Pumps- Steam generators- Intermediate loop
Efficient in uranium utilization Breeding ratio > 1Proliferation resistant Long life core > 10-15 yrs
Requirements of Innovative Small Reactors
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Steam(296℃)
Direct contact BoilingGas Lift Pump
Pb-BiControl Rod
Feed Water(220℃)
Core
Direct Contact LFR (PBWR)
proposed by J. Buongiorno, N. E. Todreas, et al., at ANS Winter Meeting, Long Beach, USA, in 1999.
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Steam Lift Pump (PBWFR)Φ5.1mx14.5mH
Forced ConvectionΦ5.2mx15.2mH
150MWe 50MWe
Reduction of component materialEconomy
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Research Projects for Development of Innovative Nuclear Technologies
by MEXT (FY2002-2004)
Pb-Bi Cooled Direct Contact Boiling Water FR (PBWFR)
1. Conceptual design 2. Pb-Bi-water direct
boiling test3. Test of steam
injection into Pb-Bi/ O-control
4. Corrosion 5. Polonium measure
ThemeTheme
Direct contact boiling/Steam lift pump performance
Core
Steam with Pb-Bi mists
Polonium measure
Corrosion Water injection/
Oxygen control
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1) Conceptual designLong life core, void reactivity and specific structural design,Safety evaluation.
2) Material and chemistryControl of oxygen potential in Pb-Bi,Compatibility of core and structural materials with Pb-Bi,Measure of Po transport into steam system.
Challenges of PBWFR Technology
3) HydraulicsLift pump performance,Suppression of carry-over of Pb-Bi mist/aerosol into steam system,Suppression of carry-under of steam bubbles into down-comer,Ultrasonic flow-meter.
4) Thermal effectDirect contact steam generation performance,Flow instability and vapor explosion.
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Pb-Bi
Reaction with air, waterOxidationOxygen controlOxygen sensorAerosol
Core designVoid reactivityPo production
Metal solutionDiffusion PenetrationCorrosionMelting point
HydraulicsTransport
ChemicalMolecular
Nuclear
Mass transportTwo-phase voidMistErosion
Phenomena
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Conceptual Design of 150MWe PBWFR
Reactor vessel炉心
Chimney
Fuel assembly
Guard vessel
Core
DHX
Supplywater
Steam
Separator/Dryer
CRDM
CRDM penetration
Ring header
Core barrel
Pipe
Pad
620˚CMax. cladding temp.
110 GWd/tBurnup
220 ˚CSupply water temperature
863 t/hSteam flow rate
1.05Breeding Ratio
450 MWtThermal power
310 ˚CCore inlet temp.
460 ˚CCore outlet temp.
15 yrsRefueling interval
296 ˚CSteam temperature
7 MPaSteam pressure
73970 t/hPb-Bi flow rate
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Total 121
Control Rod 13
Pb-Bi Shielding 30
Outer Core Fuel Assembly 42
Inner Core Fuel Assembly 36
12
0.3 w/oContents of U235
in core fuel
15.8 w/oOuter zone11.5 w/oInner zonePu
enrichment
NonLower axial30 cmUpper axialNonRadialBlanket100 cmHeight267 cmDiameterCore
Pu-U nitride(N15 100%)
Fuel
Two enriched zones.
Zones
Homogeneous core
TypeCore
Core Design
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Maximum linear power
keff
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Fuel Assembly
14
Hex. 272.0Hex. 273.0
15.9
271-12.0
5.0
5.9
Fuel 1000Fuel rod 2360
Fuel Assembly 3975
B
B
A
A
Handling head
Wrapper tube
Fuel rods Entrance nozzle Ratch spring
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$ 3 (EOL)Core, axial blanket and plenum
$ 7.4 (EOL)CoreVoid reactivity
>1.05Breeding ratio
1.5 %dk/kk’/15 yrsBurn-up reactivity loss
Breeding ratio
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Fuel Assembly
16
272.0 mmFace distance of wrapper tube 15.9 mmPitch of rod arrangement12.0 mmOuter diameter of cladding 271Number of rods 80 %Pellet smear densityGrid spacerSpacer typeDuct typeType
0.04MPaFriction pressure drop in fuel bundle46.1 %coolant
14.1 %structure
39.8 %FuelVolumetric fraction 275 mmPitch of assembly arrangement
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Additional Consideration Additional Consideration for Low Void Reactivity Corefor Low Void Reactivity Core
●Safety design demands negative void reactivity for the case of core and upper plenum region voided from considerations of core void pattern of PBWFR.
●Void reactivity (core +upper plenum) of core mentioned above is +3$.
●Considerations of core specification adequate for safety demands have been performed by core height adjustment with same core layout.
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RelationRelation of Core Height and of Core Height and Coolant Void ReactivityCoolant Void Reactivity
-15.00
-10.00
-5.00
0.00
5.00
10.00
60 70 80 90 100 110
Core Height (cm)
Coolant Void Reactivity($)
Core
Core+ Lower Blanket+ Upper Plenum
Core+ Upper Plenum
EOL(10years) Vf = 39.8%
Vioded Region
75
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Specification of Low Void Core
-5.33.0Void Reactivity(Core+Upper Plenum) ($)
5.67.4Void Reactivity(Core) ($)1.171.122Breeding Ratio (-)0.91.53Burn up Reactivity Loss (%ΔK/kk’)
3,2053,625Assembly Length (mm)331271Pin Number per Assembly (-)15.215.9Fuel Pin Pitch (mm)1212Fuel Pin Diameter (mm)
278267Core Equivalent Diameter (cm)75100Core Height (cm)1015Core Residence Time (years)
Low Void Reactivity Core
Reference CoreItem
15
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Structure in Reactor Vessel20
4230
3500
5550
2000
427 5 3
625
2050
355040304440
3380
Chimney
Inner cylinder
Water pipe
Water supply header
Core barrel
Fuel assembly
Reactor vessel
33804440
5140
Core barrel
Inner cylinder
Reactor vessel
Guard vessel
DHX
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Reactor Structure
Separatorand dryer
Support of vesselat gravity center
Guard vessel
Exchange of whole core
Upper CRDM
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Core Support Structure
Core Support Structures and Core BarrelHung from upper flangein order to pull up when refuelingSupported horizontallyby earthquake-proof pads.
Control Rod Guide TubesGuide Control Rodsfrom Head Plate to CorePenetrate Upper Structures, such as Dryer, Separator and Chimney.Supported by penetrations
(CRGTs maintain CR insertion anytime)
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111
111
11
111
11
1111
1
22
22222
22
22
22222
22
33
333
33
33
33
333
33
33
45
54
4554
45
54 4
55
4
4554
45
54
Flow AllocationFlow Allocation
Inner Core: 1,2
Outer Core : 3,4,5
10
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Power of Fuel Rod and Max. Cladding Temperature
5
4
3
2
1
Region
12
12
18
18
18
Assemblies
527585619T18.423.226.1P225510565619T18.523.528.4P247563608619T24.929.230.3P264Outer
core
619579536T28.724.920.6P249618571496T31.126.218.4P272Inner
core
FinalMiddleInitialFlow rate(kg/s)
P: Power of fuel rod (kW), T: Cladding temperature (˚C); Initial: 0 days, Middle: 2737 days, Final: 5475 days
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Plant System
RVACS
C/V
Separator/dryer
PRACS
Water supply
G/V
R/VCore
Pump
Heater
HP turbine
H2supply
Filter
LP turbine
GeneratorPump
Heater
Chimney
C/R DM
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T: Temperature (°C)P: Pressure (MPa-G)W: Flow rate (t/h)
Turbine
Generator(150We)
Thermal power450Wt
Heat balance
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Decay Heat Removal
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Sectors
Water supply headers
Nozzles
Inner headerOuter header
Performance of lift pump in chimneyPerformance of lift pump in chimney
- Uniform distribution of void fraction -High void fraction, i. e.
Low slip ratio of steam velocity to Pb-Bi velocity
Requirement in sector-type chimney
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Total lift pump head 0.198MPaChimney height 3,000mmAverage density 3,788kg/m3
(Void fraction 0.645)
Total pressure loss 0.156MPaBundle 0.081MPaAssembly 0.020MPaHD plate 0.029MPaChimney 0.025MPaDown-comer 0.00068MPa
OneOne--dimensional analysis of dimensional analysis of lift pump performancelift pump performance
Balance of head and pressure loss for Pb-Bi circuit
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Experiment of Pb-Bi-Water Direct Contact Boiling Two-phase Flow
Dump tank
Condenser
Pump
Cooler
Dryer
Fuel bundle
DirectContactboiling
Pb-Bi
Flowmeter
P
Pb-Bi-Water Direct Contact Boiling Two-phase Flow Test Apparatus
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1
2
3
5
6
7
8
4
ヒータピン(φ12×4本)
給水注入管
下降管(内径φ38.4)
下部プレナム(内径φ97.1)
四角管(内縁33×33)
チムニー管(1)(内径φ30)
チムニー管(2)(内径φ38.4)
鉛ビスマス液面
上部プレナム(内径φ283.7)
冷却コイル
9
10
図2 自然循環時の圧力損失計算モデル(鉛ビスマスのみの循環)
Pb-Bi free surface
Square duct
Lower plenum
Chimney (1)Chimney (2)
Heater pin bundle
Water supply
Upper plenumCooler
Downward pipe
Flow model
0102030405060708090
100110
Heater power Water flow rate Pb-Bi flow rateH
eate
r pow
er (k
W)
Wat
er fl
ow ra
te (k
g/h)
Pb-B
i flo
w ra
te (L
/min
)
0 60 120 180 240 300
200
300
400
500
Tem
pera
ture
(℃)
Outlet of heater pins Inlet of heater pins Outlet steam Chimney Injected waterTime (min)
7MPa
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0.5 1.0 1.5 2.0
8.0
6.0
4.0
2.0
0.5 1.0 1.5 2.0
8.0
6.0
4.0
2.0
2mm 10mm
Analysis of Pb-Bi-steam flow
Bubble diameter
0.0 0.2 0.4 0.6 0.8 1.0
Void fraction
Pb-Bi-steam 2-d two-phase flow in chimney
Key issues:-Suppression of carry-under of bubbles-Estimate of bubble diameter
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Removal of Pb-Bi mists
Dra
100500
500
2000 φ400
φ400
φ300
Dra
Sep
Dryer
Drain
Separator
Pb-Bi free suface
I.D.40
0
I.D.100
Steam flow
Steam flow
Porous plate
Pocket
Steam flow
Dryer
Cyclone separator
Chevron dryer
Drain
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Estimate of Pb-Bi mists and Pollonium
1.1×108Bq/sTransport into steam system
1.06×1011Bq/kg
Concentration in Pb-Bi
1.5×1017BqProduction
Requirement 1) Additional precipitation device2) Ceramic coated turbine blades
2.0x10-4% lower than 2.0%-5.0% in LWR
Ratio of mist flowrate to steam flowrate
4.8x10-4 kg/s or 15.2 t/y
Flow rate
Separator 95.5%, Dryer 2.6%
Removal efficiency
Mist flow rate Polonium
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Steam flow in dryer
Flow velocity distribution [m/s]
Flow velocity vector
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Droplet measurement and Electro-static precipitation
Design consideration is for a representative PBWFR condition
ESP System
PDA System
Comparison PBWFR Experiment
Velocity 0.6 m/s up to 0.1 m/sMedium Steam Argon GasPressure 7 Mpa 0.1 MpaTemperature 296 C 180 CFlowrate 329400 L/mnt 0.5 - 2 L/mnt
Glass wall
Dump Tank
Level meter tank
Test section
Ar gas injection
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A design concept of PBWFR has been formulated with design parameters identified, and will be modified by the results of the following studies:
・ Two-phase flow test in the chimneyfor structure design of chimney with gas lift pump,
• Pb-Bi droplet removal testfor the reduction of carry-over and Po transport rate into steam system,
• Pb-Bi-water direct contact boiling testfor stable boiling and Pb-Bi circulation under
practical conditions,• Corrosion/steam injection tests
for corrosion-resistant steels, oxygen control/measurement method and the other Pb-Bi technology.
Concluding remarks