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Brookhaven Science AssociatesU.S. Department o f Energy
GENERATION IV NUCLEAR ENERGY SYSTEMSHOW THEY GOT HERE AND WHERE THEY ARE GOING
GENERATION IV NUCLEAR ENERGY SYSTEMSGENERATION IV NUCLEAR ENERGY SYSTEMSHOW THEY GOT HERE AND WHERE THEY ARE GOING HOW THEY GOT HERE AND WHERE THEY ARE GOING
David J. Diamond
Brookhaven National Laboratory
Energy Sciences and Technology Department
Nuclear Energy and Infrastructure Systems Division
Presented at the University of Tennessee April 30, 2003
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Slide 2
OUTLINE OF PRESENTATIONOUTLINE OF PRESENTATION
n Introduction to the Gen IV (long-term) Nuclear Energy Systems
n The Roadmap - how we got to the Gen IV concepts
n The Not-Gen IV Nuclear Energy Systemsaka the international near-term deployment concepts
n What do the Gen IV concepts look like; what are some of their R&D needs
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Slide 3
GENERATION IV NUCLEAR ENERGY SYSTEMSGENERATION IV NUCLEAR ENERGY SYSTEMS
Sodium Fast Reactor (SFR)
Gas-Cooled Fast Reactor (GFR)
Molten Salt Reactor (MSR)
Supercritical
Water Reactor (SCWR)
Very High Temp.Gas Reactor (VHTR)
Lead-alloy Fast Reactor (LFR)
R&D Applications
Size Fuel Cycle
Neutron Spectrum
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Slide 4
GENERATION IV NUCLEAR ENERGY SYSTEMSGENERATION IV NUCLEAR ENERGY SYSTEMS
ClosedFastSodium Fast Reactor (SFR)
ClosedFastGas-Cooled Fast Reactor (GFR)
ClosedThermalMolten Salt Reactor (MSR)
Open,
Closed
Thermal,
Fast
Supercritical
Water Reactor (SCWR)
OpenThermalVery High Temp.Gas Reactor (VHTR)
ClosedFastLead-alloy Fast Reactor (LFR)
R&D Applications
Size Fuel Cycle
Neutron Spectrum
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Slide 5
GENERATION IV NUCLEAR ENERGY SYSTEMSGENERATION IV NUCLEAR ENERGY SYSTEMS
AdvancedRecycle
Electricity, Actinide Mgmt.
Med toLarge
ClosedFastSodium Fast Reactor (SFR)
Fuels, Materials,Safety
Electricity, ActinideMgmt., Hydrogen
MedClosedFastGas-Cooled Fast Reactor (GFR)
Fuel, Fueltreatment,Materials, Safetyand Reliability
Electricity, ActinideMgmt., Hydrogen
LargeClosedThermalMolten Salt Reactor (MSR)
Materials, SafetyElectricityLargeOpen,
Closed
Thermal,
Fast
Supercritical
Water Reactor (SCWR)
Fuels, Materials,H2 production
Electricit y, Hydrogen,Process Heat
MedOpenThermalVery High Temp.Gas Reactor (VHTR)
Fuels, Materialscompatibility
Electricity, ActinideMgmt., Hydrogen
Small toLarge
ClosedFastLead-alloy Fast Reactor (LFR)
R&D Applications
Size Fuel Cycle
Neutron Spectrum
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Slide 6
THE TECHNICAL ROADMAPTHE TECHNICAL ROADMAP
n Discusses the benefits, goals and challenges, and the importance of thefuel cycle
n Describes evaluation and selection process
n Introduces the six Generation IV systems chosen by the Generation IVInternational Forum
n Surveys system-specific R&D needs for all six systems
n Collects crosscut ting R&D needs
n GIF countries will choose the systems they will work on
n Programs and projects wil l be founded on the R&D surveyed in theroadmap
n Information available at gif.inel.gov/roadmap/
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Slide 7
TECHNOLOGY GOALSTECHNOLOGY GOALS
n Sustainability1. Provide sustainable energy generation that meets clean air
objectives and promotes long-term availability of systems andeffective fuel utilization for worldwide energy production
2. Minimize and manage their nuclear waste and notably reduce the
long term stewardship burden, thereby improving protection for
the public health and the environment
n Safety and reliability
3. Operations will excel in safety and reliability
4. Will have a very low likelihood and degree of reactor core damage
5. Will eliminate the need for offsite emergency response
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TECHNOLOGY GOALSTECHNOLOGY GOALS
n Economics6. Will have a clear life-cycle cost advantage over other energy
sources
7. Will have a level of financial risk comparable to other energyprojects
n Proliferation resistance and physical protection
8. Will increase the assurance that they are a very unattractive andthe least desirable route for diversion or theft of weapons-usable
materials, and provide increased physical protection against actsof terrorism
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Slide 9
INTERNATIONAL NEAR-TERM DEPLOYMENT (1/2)INTERNATIONAL NEAR-TERM DEPLOYMENT (1/2)
n Deployment by 2015
n Industry involvement
n Improvement over current advanced LWR performance
n Advanced Boiling Water Reactors
• ABWR-II• ESBWR
• SWR-1000
• HC-BWR
n Modular High-Temperature Gas-Cooled Reactors• GT-MHR
• PBMR
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Slide 10
INTERNATIONAL NEAR-TERM DEPLOYMENT (2/2)INTERNATIONAL NEAR-TERM DEPLOYMENT (2/2)
n
Advanced Pressure Tube Reactor • ACR-700
n Advanced Pressurized Water Reactors
• AP-600• AP-1000• APR-1400
• APWR+• EPR
n Integral Primary System Reactors
• CAREM• IMR
• IRIS• SMART
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Slide 11
GEN IV NUCLEAR ENERGY SYSTEMSGEN IV NUCLEAR ENERGY SYSTEMS
n Very High Temp. Gas Reactor (VHTR)
n Gas-Cooled Fast Reactor (GFR)
n Supercritical Water Reactor (SCWR)
n Sodium Fast Reactor (SFR)
n Lead-alloy Fast Reactor (LFR)
n Molten Salt Reactor (MSR)
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Slide 12
SEQUENCED DEVELOPMENT OF HIGH TEMPERATUREGAS COOLED NUCLEAR ENERGY SYSTEMSSEQUENCED DEVELOPMENT OF HIGH TEMPERATUREGAS COOLED NUCLEAR ENERGY SYSTEMS
PMR
GFR
> 950°C for VHTheat process
Fast neutrons &integral fuelcycle for highsustainability
VHTR
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Slide 13
VHTR FOR HYDROGEN PRODUCTIONVHTR FOR HYDROGEN PRODUCTION
n Hydrogen demand is already large and growing rapid ly
• Heavy-oil refining consumes 5% of natural gas for hydrogen production
n Energy securi ty and environmental quality motivate hydrogen as an alternative to oilas a transportation fuel
• Zero-emissions
• Distributed energy opportunity
n Water is the preferred hydrogen“fuel”• Electro lysis using off-peak
power • High-temperature electrolysis• High-temperature
thermochemical water split ting
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Slide 14
VERY HIGH TEMPERATURE REACTOR (VHTR)VERY HIGH TEMPERATURE REACTOR (VHTR)
Characteristics
•He coolant•1000°C outlet temperature•Reactor coupled to H2
production facility•600 MWth, nominally basedon MHTGR
•Coated particle fuel,graphite block (or pebble?)core
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Slide 15
Reactor CavityCooling System
Reactor Pressure
Vessel
Control Rod Drive
Stand Pipes
Power Conversion
System Vessel
Floors Typical
Generator
RefuelingFloor
Shutdown Cooling
System Piping
Cross Vessel
(Contains Hot &
Cold Duct)
35m(115ft)
32m(105ft)
46m(151ft
GT-MHR REACTOR BUILDINGGT-MHR REACTOR BUILDING
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Slide 16
Control Rod
Drive Assembly
RefuelingStand Pipe
Control RodGuide tubes
Cold leg Core
Coolant Upper
Plenum
Central ReflectorGraphite
Annular shaped
Active Core
Outer Side ReflectorGraphite
Core Exit Hot Gas
Plenum
Graphite Core
Support Columns
Reactor Vessel
Upper PlenumShroud
Shutdown CoolingSystem ModuleHot Duct
Insulation
Module
Cross Vessel
Nipple
Hot Duct
StructuralElement
Metallic Core
Support Structure
Core Inlet Flow
CoreOutletFlow
Insulation Layer for Metallic
Core Support Plate
Upper Core Restraint
Structure
Control Rods
7m(23 ft)
23.7m(78ft)
2.2m(7ft)
8.2m(27ft) Dia
Vessel Flange
Upper plenum - hot plume
mixing - “LOF”
Core - depressurized cooldown
Flow between hotter/ cooler
channels - “LOF”
Lower plenum - hot
jet mixing
Natural convection and thermal radiation
Core flow - normal operation
GT-MHRGT-MHR
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Slide 17
CORE FLOW ISSUES DURING NORMAL OPERATIONCORE FLOW ISSUES DURING NORMAL OPERATION
n Calculation of the coolant channel temperatures during normal operation
• Significant local variations in power occur across the core due the non-uniformlocation of the reflectors, control rods, and burnable poison assemblies and due tothe fuel loading
• Power variations are amplified in the hot channels due to the buoyancy resistance
• Therefore the coolant temperatures can vary by more than + or - 200°C from theaverage
n Calculation of the core lower plenum flow mixing and pressure drop
• Hot jet mixing, complex 3-dimensional flow around the core suppor ts, and the flowacceleration near the hot duct need to be calculated
n Calculation of the hot duct coo lant mixing and insulation effectiveness• Permeation o f the hot gas into the insulation is a concern
• The entrance condit ions are somewhat uncertain, but the flow must be well mixed bythe time it reaches the turbine
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Slide 18
Thermal-hydraulic Issues
n Mixing of the gases during bypassevents
n Flow distributions among therecuperators and recuperator efficiency
n Hot streaks at the turbine inlet
Generator
Thrust Bearing
Turbine
High Pressure
Compressor
Recouperator
Recouperator
Low Pressure
Compressor
Precooler/ Intercooler
Cold Gas to Reactor
Hot Gas from Reactor
PCS Vessel
34m(112ft)
8.2m(27ft) Dia.
Vessel Flange
POWER CONVERSION UNITPOWER CONVERSION UNIT
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Slide 19
THERMAL-HYDRAULIC ISSUES - ACCIDENT CONDITIONSTHERMAL-HYDRAULIC ISSUES -
ACCIDENT CONDITIONS
n
Rejection of the heat by natural convection and thermal radiation from the reactor pressure vessel outer wall to the passive cooling system
• Local effects around the hot duct need to be cons idered
• Some separate effects proof testing may be needed
n Reliability , robustness, and effectiveness of the Reactor Cavity Cooling System
n Flow through the core during a loss of circulation accident
• Up flow in the hot channels and down flow in the cool channels results in hotplumes in the upper plenum
• The hot and cold channel flow dist ribution and the upper plenum mixing areuncertain
• Low Reynolds number flow with turbulent, transitional, and/or laminar flow,
buoyancy effects, and gas property variations
n Core cool down during a LOCA
n Air or water ingress during a LOCA
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Slide 20
GAS-COOLED FAST REACTOR (GFR)GAS-COOLED FAST REACTOR (GFR)
Characteristics
• He (or SC CO2) coolant, direct
cycle energy conversion
• 850°C outlet temperature
• 600 MWth /288 MWe
• U-TRU ceramic fuel in coated
particle, dispersion, or
homogeneous form
• Block, pebble, plate or pin core
geometry
• Combined use of passive and
active safety systems
• Closed fuel cycle system with fullTRU recyc le
• Direct Brayton cycle energy
conversion
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Slide 21
ADVANTAGES OF GFR ADVANTAGES OF GFR
n
GFRs share the sustainability attributes of fast reactors• Effective fissioning of Pu and minor actinides
• Ability to operate on wide range of fuel compositions (“ dirty fuel” )
• Capacity for breeding excess fissile material
n Advantages offered by use of He coolant• Ease of in-service inspection
• Chemical inertness
• Very small coolant void reactivi ty (<ßeff )
• Potential for very high temperature and direct cycle conversion
n High temperature potential opens possibil ities for new applications,including hydrogen production
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Slide 22
GFR R&D NEEDSGFR R&D NEEDS
n Safety case difficult wi th low thermal inertia and poor heat transfer
properties of coolant
• Reliance on active and “ semi-passive” systems for decay heat removal• Passive reactivity shutdown is also targeted
n High actinide-density fuels capable of withstanding high temperature and
fast fluence
• Modified coated particle or dispersion type fuels, e.g., – (U,TRU)C/SiC – (U,TRU)N/TiN
• Fuel pins with high-temperature cladding, e.g., infiltrated kernel particle
n Core structural materials for high temperature and fast-neutron fluenceconditions (ceramics, composites, refractory alloys)
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Slide 23
FUEL / CORE CONFIGURATIONSFUEL / CORE CONFIGURATIONS
n GFR
• Metal or ceramic matrix (similar to prismatic)
• Pin, plate types (ceramic, metallic)
• Pebble/particle
C o m p o s i t e C e r a m i c s
F u e l E l e m e n t C o r e L a y - o u t
Co r e V e s s e l
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Slide 24
SCWR: GENERAL CHARACTERISTICSSCWR: GENERAL CHARACTERISTICS
n
LWR operating at higher pressure (>22.1 MPa) and temperature (280-550°C)• Operating condi tions with fossil plant experience
n Higher thermal efficiency (44% vs. 33%)
n No change of phase
• Larger enthalpy rise in core• Lower flow rate (~10% of BWR)
• Lower pumping power (smaller pumps)
n Simplified direct cycle system• No recirculation
• Smaller reactor pressure vessel/containment
n Thermal or fast spectrum possible• Fuel cycle flexibili ty
Improved Economics
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Slide 25
SCWR: OPTIMIZATION OF LWR TECHNOLOGYSCWR: OPTIMIZATION OF LWR TECHNOLOGY
Reactor
Turbine/Generator
Reactor
Turbine/Generator
ReactorSteam-waterseparation system
Recirculationsystem
Turbine/Generator
ReactorSteam-waterseparation system
Recirculationsystem
Turbine/Generator
Reactor
Steam generatorPressurizer
Turbine/Generator
Reactor
Steam generatorPressurizer
Turbine/Generator
Reactor
Turbine/Generator
Reactor
Turbine/Generator
ReactorSteam-waterseparation system
Recirculationsystem
Turbine/Generator
ReactorSteam-waterseparation system
Recirculationsystem
Turbine/Generator
Reactor
Steam generatorPressurizer
Turbine/Generator
Reactor
Steam generatorPressurizer
Turbine/Generator
Reactor
Turbine/Generator
Reactor
Turbine/Generator
ReactorSteam-waterseparation system
Recirculationsystem
Turbine/Generator
ReactorSteam-waterseparation system
Recirculationsystem
Turbine/Generator
Reactor
Steam generatorPressurizer
Turbine/Generator
Reactor
Steam generatorPressurizer
Turbine/Generator
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Slide 26
SCWR: EFFECT OF SIMPLIFICATIONSCWR: EFFECT OF SIMPLIFICATION
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Slide 27
Fuel assembly
SCWR NEUTRONIC DESIGNSCWR NEUTRONIC DESIGN
n Considerations with core design
• Large change in density axially
• Average coolant density higher thanin BWR
• Downward flow in water rods
• Other moderators (BeO, ZrH2
)
• Square or hexagonal geometry
Water rod
nSafety consideration
•Rod ejection accident•Negative moderator reactivi ty coefficient
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Slide 28
BASIC DATA - HEAT TRANSFERBASIC DATA - HEAT TRANSFER
Heat-transfer data at prototypical
SCWR condi tions (i.e.,
supercritical water, complex
bundle geometry, high heat flux)
are needed.
Single-phase heat transfer: Data exist for either simpleround tubes and/or surrogatefluids. Existing SCW heat-transfer database and
correlations are inconsistent.
Existing correlations and models for SCW heat transfer exhibi t large
discrepancies and diverging trends
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Slide 29
CODES - NUMERICAL INSTABILITIESCODES - NUMERICAL INSTABILITIES
Large (albeit continuous) variation of the thermo-physical properties…
… may result in code execution failures.
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Slide 30
SODIUM-COOLED FAST REACTOR (SFR)SODIUM-COOLED FAST REACTOR (SFR)
Characteristics•Sodium coolant, 550°C Tout
•150 to 1500 MWe•Pool or loop plantconfiguration
•Intermediate heat transportsystem
•U-TRU oxide or metal-alloyfuel
•Hexagonal assemblies of fuel pins on triangular pitch
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Slide 31
SFR SAFETY R&D NEEDSSFR SAFETY R&D NEEDS
n Demonstration of passive safety design: providing assurance that the physical
phenomena and related design features relied upon to achieve passive safety areadequately characterized
• Axial fuel expansion and radial core expansion
– Experimental data plus deterministic models required for accurate corerepresentation (particularly, minor-actinide-bearing fuels)
– Reduce uncertainties in T-H quantities by using more detailed models- Multi-pin subassembly, full assembly -by-assembly, coupled neutron ics-
thermal-hydraulic calculation
- Accurate duct -wall and load pad temperatures required for calculatingbending moments in each subassembly to characterize core restraint andexpansion
- CFD tools for benchmark calculations or routine design calculations?
• Self-activated shutdown systems
• Passive decay heat removal systems – CFD models useful for resolution of complex natural circu lation flow paths
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Slide 32
SFR SAFETY R&D NEEDS (CONT’D)SFR SAFETY R&D NEEDS (CONT’D)
n Accommodation of extremely low probabili ty but higher consequenceaccident scenarios
• Demonstrate that passive mechanisms exist to preclude recriticality ina damaged reactor
• Show that debris from fuel failure is coolable within the reactor vessel
n
Implication for safety analysis tools• Requires analytical and experimental investigations of mechanism s
that will ensure passively safe response to bounding events that leadto fuel damage
– e.g., out-of-pile experiments involving reactor materials arerecommended for metal fuels
• Local feedback and material motion modeling required
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Slide 33
LEAD-COOLED FAST REACTOR (LFR)LEAD-COOLED FAST REACTOR (LFR)
Characteristics
• Pb or Pb/Bi coolant• 550°C to 800°C out let temperature
• Fast Spectrum
• Mult i-TRU recycle
• 50–1200 MWe
• 15–30 year core li feOptions
• Long-lif e (10-30 yrs), factory -fabricated
battery (50-150 MWe) for smaller grids
and developing countries
• Modular system rated at 300-400 MWe
• Large monol ith ic p lant at ~1,200 MWe• Long-term, Pb option is intended for
hydrogen generation – outlet
temperatu re in the 750-800oC range
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Slide 34
CHARACTERISTICS OF LEAD ALLOY COOLANTCHARACTERISTICS OF LEAD ALLOY COOLANT
n Low Neutron Absorption and Slowing Down Power
• Allow to open the lattice, increase coolant volume fraction absent a
neutronics penalty – pumping requirements also dictate open lattice
• Facili tates natural circulation
n High Boiling Temperature at Atmospheric Pressure (~1700°C)
• Unpressurized primary (precludes loss of coolant accident initiator)• Margins are available to employ passive safety – based on
thermo/structural feedbacks
• Potential to raise core outlet temperature (~800°C suitable for H2
production and other process heat missions)
n Non-vigorous reaction with air and water
• Potential to simplify heat transport circuits
• Potential to simplify refueling approaches
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Slide 35
MOLTEN SALT REACTOR (MSR)MOLTEN SALT REACTOR (MSR)
HeatExchanger
Reactor
Graphite
Moderator
SecondarySalt Pump
Off-gasSystem
PrimarySalt Pump
PurifiedSalt
ChemicalProcessing
Plant
Turbo-Generator
FreezePlug
Critically Safe, Passively Cooled Dump Tanks(Emergency Cooling and Shutdown)
Steam Generator
NaBF_
NaFCoolant Salt
4
72LiF _ Th
Fuel Salt
_ BeF F _ UF4 4
566Co
704Co
454Co
621Co
538 Co
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Slide 36
MOLTEN SALT REACTOR (MSR)MOLTEN SALT REACTOR (MSR)
Characteristics
•Molten fluoride salt fuel•700–800°C outlet temperature• Intermediate heat transpor t
circuit•~1000 MWe or larger •Low pressure (<0.5 MPa)•Graphite core struc ture
channels flow of actinidebearing fuel
Safety analysis issues•Modeling of nuclear, thermal,
& physio-chemical processes(e.g., FP and MA solub ilit y,nob le metal FP plate-out, …)
•Lack of established analysiscapabilities
•Regulatory framework notdefined