Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer O f N u c l e a r S y s t e m s W i s c o n s i n I n s t i t u t e Advanced Nuclear Energy Systems: Heat Transfer Issues and Trends Michael Corradini Wisconsin Institute of Nuclear Systems Nuclear Engr. & Engr. Physics University 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
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