advanced nuclear energy systems: heat transfer issues and
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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
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)
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
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
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
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
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.
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
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
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
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
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
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.
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)
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
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
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
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)
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