advanced nuclear energy systems: heat transfer issues and
TRANSCRIPT
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Advanced Nuclear Energy Systems:Heat Transfer Issues and Trends
Michael CorradiniWisconsin Institute of Nuclear Systems
Nuclear Engr. & Engr. PhysicsUniversity of Wisconsin - Madison
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
ENERGY SUSTAINABILITYConditions Needed for Energy Sustainability:
Economically feasible technologyMinimal by-product streamsAcceptable land usage“Unlimited” supply of energy resourceNeither the power source nor the technology to exploit it can be controlled by a few nations/regions
Nuclear energy systems meet these conditions and can be part of the solution for future energy growth (Electricity growth estimates range 1 - 4.5%/yr)
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Evolution of Nuclear Power Systems
1960 1970 1980 1990 2000 2010 2020 2030
Gen IV
Generation IVGeneration IV• Enhanced
Safety• More
economical• Minimized
Wastes• Proliferation
Resistance
• Enhanced Safety
• More economical
• Minimized Wastes
• Proliferation Resistance
Gen I
Generation IGeneration IEarly Prototype
Reactors
•Shippingport•Dresden,Fermi-I•Magnox
Gen II
Generation IIGeneration IICommercial Power
Reactors
•LWR: PWR/BWR•CANDU•VVER/RBMK
Gen III
Generation IIIGeneration IIIAdvanced
LWRs
•System 80+•ABWR
•AP1000•ESBWR
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Advanced Light Water Reactors: AP1000-Enhanced Passive Safety
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Advanced Light Water Reactors:ESBWR-Simplified Operation & Safety
Natural Circulationin the Vessel
Passive Safety Systems
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Advanced Light Water Reactors:Multiphase Heat Transfer Issues
Passive systems can simplify construction and operation but may complicate engr. analysesNatural-circulation multiphase flow in complex geometries (plant geom. dependent)Condensation heat transfer with non-condensible gases in reactor containmentMultiphase/multicomponent heat transfer in safety analyses beyond the ALWR design base
In-vessel lower head cooling & Ex-vessel debris coolabilityMultiphase/multicomponent direct-contact heat-exchange
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
BWR/6
ESBWR
ABWR
Steam g
A More Advanced LWRThe next logical step in path toward simplification ?
PWR
SCWRA boiling water reactor …without the boiling.
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
SUPERCRITICAL WATER REACTOR
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Heat Transfer in SCW Reactor:
500
600
700
800
900
1000
1100
1200
1300
1400
0 0.5 1 1.5 2 2.5 3Height of the core [m]
Tem
pera
ture
[K]
0
5000
10000
15000
20000
25000
30000
35000
40000
Line
ar h
eat g
ener
atio
n [W
/m]
Jackson: 1.53Jackson: 1.34Jackson: 1.23Bishop: 1.23Bishop: 1.34Bishop: 1.53Qlinear
P/D
Absence of boiling crisis (CHF), but with heat transfer degradation
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
SCW Flow Control and Instabilities
0
100
200
300
400
500
600
700
800
900
0 5 10 15 20 25 30Power (kW)
G (k
g/m
2 s)
20
30
40
50
60
70
80
90
100
110
Tem
pera
ture
(o C)
Mass Velocity
Hot Side Temperature
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Nuclear Fuel RecycleSpent Fuel From
Commercial Plants
Direct Disposal Conventional
Reprocessing
PUREX
SpentFuel
Pu UraniumMOX
LWRs/ALWRs
U and PuActinidesFission Products
RepositoryRepository
Less U and PuActinides
Fission Products
Advanced, Proliferation-Resistant
Recycling AFCI
ADS Transmuter
Trace U and PuTrace ActinidesLess Fission Products
Repository
Gen IV Fast Reactors
Once ThroughFuel Cycle
European/JapaneseFuel Cycle Advanced Proliferation Resistant
Fuel Cycle
Gen IV Fuel Fabrication
LWRs/ALWRs
Advanced Separations
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Liquid-Metal-Cooled Fast Reactor (e.g. LFR)
Characteristics• Pb or Pb/Bi coolant• 550°C to 800°C outlet
temperature• 120–400 MWe
Key Benefit• Waste minimization and
efficient use of uranium resources
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Liquid Metal-Water Direct Contact HX
L
Lsub
Lsat
Lsup
Liquid Metal
SteamAdvantages:
- Vigorous interaction between the liquid metal and the water
- Excellent contact so smaller volume is required to transfer the same amount of energy.
- Potential replacement of IHX loop.
=> Need to determine the local heat transfer coefficient and flow stability for a range of flow rates and regimes.
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Void [cm]
0 .0 0 .1 0 .2 0 .3 0 .4 0 .5 0 .60 .0 0
0 .0 5
0 .1 0
0 .1 5
0 .2 0
0 .2 5
0 .3 0
E x p t. P = 0 .1 M p a
α wat
er
D is ta n c e a b o v e in je c to r z [m ]
DCHT via Xray Imaging
0
1000
2000
3000
0 2.5 5 7.5 10 12.5 15Distance from the Injector [cm]
HTC(w/m2K)
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Very-High-Temperature Reactor (VHTR)
Characteristics• Helium coolant• 1000°C outlet temp.• 600 MWth• Water-cracking cycle
Key Benefit• Hydrogen production
by water-cracking
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
GAS-COOLED REACTOR
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Process Heat for Hydrogen Production
Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen
H2O22
1
900 C400 C
Rejected Heat 100 CRejected Heat 100 C
S (Sulfur)Circulation
SO2+H2O+O22
1H2SO4
SO2+
H2OH2O
H2
I2+ 2HI
H2SO4
SO2+H2OH2O
+
+ +
I (Iodine)Circulation
2H I
I2
I2
WaterWater
Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen
H2O22
1O22121
900 C400 C
Rejected Heat 100 CRejected Heat 100 C
S (Sulfur)Circulation
SO2+H2O+O22
1H2SO4
SO2+
H2OH2O
H2
I2+ 2HI
H2SO4
SO2+H2OH2O
+
+ +
I (Iodine)Circulation
2H I
I2
I2
WaterWater
L
Liquid Metal
Hydrogen
CxHy
Carbon Recycle
200 C 1000 C
Iodine/Sulfuric-AcidThermochemical
Process
LM Condensed Phase Reforming (pyrolysis)
Aqueous-phase Carbohydrate
Reforming (ACR)H2, CO2
CATALYST
AQUEOUS CARBOHYDRATE
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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer
Of Nucl ear Sys te
ms
Wis
consin Instit u
t e
Micro-Nuclear Power Applications (NAE-Blanchard)
Self-Reciprocating Cantilever Wireless Transmitter
Micro Thermoelectric or Thermionic Generator
N
P
Direct Conversion(Electricity from radiation used
to create ion-hole pair in PN Jnc)