Design, Test and Demonstration of Saturable- Core Reactor HTS Fault Current Limiter
Advanced Reactor Demonstration Project Overview
Transcript of Advanced Reactor Demonstration Project Overview
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a TerraPower & GE-Hitachi technology
Advanced Reactor Demonstration Project
Overview
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Advanced Reactor Demonstration Program (ARDP)
demonstration goals
• Demonstrate the ability to design, license, construct, startup and
operate our Natrium™ Advanced Reactor
• Build the supply chain for sodium fast reactors in the United States
• Lower emissions by initiating the deployment of a fleet of Natrium
reactors – Demo will show that we can build these plants
economically and that they will be attractive for future
owner/operators
• Development of new jobs and a stronger economy
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Elements of the Natrium™ ARDP Offering
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• Strong private financial backing
• Design, NRC Part 50 licensing, Procurement, Construction and Startup of Natrium Demonstration reactor 840 MWt through fuel loading within 7 years
• Support Development of HALEU metal fuel supply chain
o Providing funding for first year of development in two cascades of 120 AC100M centrifuges that would add 12 MTU/year of capacity at 19.75 wt. % U235.
o Design, license and construct a fuel fabrication facility for HALEU metallic fuel
• Continue development of TP advanced fuel and material development and qualification program
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Team Members
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Why Natrium™ technology?
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It is the best option for deploying advanced nuclear power given increasing demand for carbon-free energy and a growing mix of renewable sources because it:
• Simplifies construction and architecture compared to previous reactor types
• Offers a cost-competitive, flexible technology that supports load following, energy storage and industrial process heat applications
• Brings step-change improvements in capital and operational costs
• Provides a utility-scale decarbonization solution that can make a meaningful impact on efforts to mitigate climate change
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Fuel and Material
Development &
Qualification
Team Natrium
ARDP Natrium Demonstration Project Level 1 Schedule
Operations Programs
and Startup
Procurement &
Construction
Equipment Testing &
Qualification
Licensing
Methods
Development
Plant Design
Subproject1 2 4 5 6 7 8
Program Management
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Q4Q3Q2Q1Q4Q3Q2Q1Q4Q3Q2Q1Q4Q3Q2Q1Q4Q3Q2Q1Q4Q3Q2Q1Q4Q3Q2Q1Q4Q3Q2Q1Q4Q3
0
Pre-Licensing
Engagement with
NRC
Team Natrium
Awarded and
Contract in Place
Site
Selected
Final (100%)
Design Complete
Start of Human
Factors Engineering
Construction
Complete
First Safety
Concrete
Begin Site
Preparation
NRC Review NRC Review
Sodium Fill,
Fuel Staging
First Operator
Training Class
V&V Testing Complete
Early Supplier
Engagement
Start of FSAR
Preparation
Factory
Acceptance
Testing Complete
V&V Test Planning
Complete
LEGEND
Engineering
Key Project Milestone Logic Tie
R&D
Construction
Partnership
Licensing
Supply Chain
OperationsOperations Programs
Class 3/4 Cost and
Schedule Estimates
Complete
Fuel Supply
Submit License
Application for
Fab. Facility
Fuel Fabrication,
HALEU Supply, Site
Selection Planning
Design Complete/
Begin Facility
Construction
Initial Core Load
Delivery Complete
Shipping Containers
Licensed & Fabricated
Shipping Container
Tests Complete; Design
Submitted to NRC
Continue Fuel Fab.
for Reloads
Management
Plan Issued
Definitive Cost and
Schedule Estimates
Complete
Demo Construction
ApprovedPreliminary
(60%) Design
Complete
Detailed
(95%) Design
Complete
Methods V&V
Complete
Construction
Permit Issued
by NRC
Regulatory
Engagement Plan
Complete
State and Local
Construction
Permits Issued
Operating
License Issued
by NRC
Development
Testing Complete
Qualification
Testing Complete
Procurement
Plans IssuedReactor
Vessel Set
Simulator
OperationalStart Training and
Procedure
Development
Initial Operator
Training
Complete
Begin Equipment
Turnovers
Full Power
Operations
Process
Development
Complete
Type 1B LTAs
Ready for
Insertion
Fuel Load,
Low Power
Operations
Large Sodium Test
Facility Operational
Fab. Facility
Operational
Start Fuel
Fabrication
Start of
PSAR
Preparation
Initiate Long-Lead
Equipment Procurement
Design Reference 1
Complete
Testing for PSAR
Complete
Methodology Reports
for CPA Submitted
Enter Utility
IRP Process
PSAR / Construction
Permit Application
(CPA) Submission
Start/Finish
FSAR / Operating
License Application
(OLA) Submission
Start/Finish
PIE and TREAT
Testing of High Burnup
Fuel Complete
Resume Legacy Fuel
PIE Program at INL
Start of Transient Test
Program
(TREAT Reactor)
Fuel Licensing
Activities Complete
TREAT Sodium
Loop Available
Demonstration
Testing Complete
Final Delivery
of Long-Lead
Equipment
Construction
Execution Plan Issued
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Schedule and Cost Estimate Methodology
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• Assumes a defined spending plan with consistent source of funds
• Jointly developed by TP, GEH and Bechtel based on past experiences
• Licensing schedule has been discussed several times with NRC “aggressive but achievable”
• Design to minimize construction time
• AACE Class 3 / 4 cost estimate and schedule by end of budget period 2
• AACE Definitive cost estimate and schedule for construction will be provided in 4th budget period
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Simple Nuclear Systems
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Natrium Radiant Vessel Cooling
• Zero ASME Sect. III Pipe Welds• Atmospheric Pressure (<1 PSI)• Unlimited Air-Cooled Heat Sink Supply• Fully Passive (Always in Operation)• Singular Rugged System
LWR Emergency Core Cooling
• 2600+ ASME Sect. III Pipe Welds• High Pressure Injection (1000+ PSI)• Large Water Inventory Requirements • Active Valve and Pump Operation• Multiple Trains and Sub-systems
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Simple Nuclear Buildings
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Simple Nuclear Construction
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Customers?
• Marketing to US Utilities
• About 10 US Utilities have joined our Utility Advisory Board
• In discussions with a potential owner/operators for the demonstration plant
• Key success criteria –
– Natrium can be located anywhere that meets the NRC criteria, but has added value in markets that have a high penetration of renewables, that both need a stable baseload and need power on demand when solar and wind are not available.
– Strong political support, especially at the state and local levels
– Strong workforce
– EPRI Siting Guide
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Licensing Strategy
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• Team Natrium selected the 10 CFR 50 licensing process due to the time requirements on the program. 10 CFR 50 allows you to start construction earlier.
• The Preliminary Safety Analysis Report will be submitted with a Part 50 Construction Permit Application (CPA). The PSAR is currently organized consistent with the draft PSAR/FSAR outline and guidance provided by an NRC letter dated April 15, 2020, titled “Updated Draft Outline for Licensing Modernization Project Advanced Reactor License Applications”
• The Final Safety Analysis Report will be submitted with the Operating License Application
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Natrium Reactor Planned NRC Interactions
Environmental (2021-2022)
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• Site Selection Process
• Environmental Coordination State and Federal
• Environmental Need for Power and Alternate Analysis
• Severe Accident Mitigation Analysis
• Environmental – Fuel Cycle Impacts
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Planned NRC Interactions Safety/Programs (2021-2027)
• Quality Assurance – NRC currently reviewing
• Safeguards Information (SGI) Plan
• Probabilistic Risk Assessment (PRA)
• Natrium Demo Plant
• Applicability of Regulations
• Engineering Computer Codes for Natrium
• M++ (Mongoose sub channel code) Thermal Hydraulic Topical
• Risk Informed Performance Based Preliminary Design Criteria
• Plant-Level Risk-Informed Performance-Based SSC’s Classification
• Energy Island Decoupling
• Consensus Codes and Standards
• Source Term Methodology
• Design Basis Accident Methodology
• PSAR Chapter 1 – Plant and site overview
• Licensing Basis Events with and without releases
• Emergency Preparedness
• Metal Fuel Operating Experience
• Radiological Release Consequences Methodology
• Reactor Stability Methodology
• Partial Flow Blockage Methodology
• Regulatory Exemptions
• Fuel Methodology
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Key Licensing Milestones (2023 – 2028)
• Construction Permit Application and PSAR Submittal – August 2023
• License to Construct – March 2025
• Operating License Application and FSAR Submittal – March 2026
• License of Operate – March 2028
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Nuclear redefined• Eliminates nuclear “sprawl”
✓ Design to cost✓ Simplicity✓ Rapid construction✓ Design specific staffing
• ~41% net thermal efficiency
Redefining what nuclear can be…
Integrating with renewables• Zero emission dispatchable resource • Price follower… w/ reactor at 100% power 24/7• 345 MWe nominal• Flex to 500 MWe for 5.5 hours through energy storage
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Rx Building
Fuel Building
Fuel Aux. Building
Rx Aux. Building
NI Power Distribution Center & Controls
Control Building
Warehouse& Admin
Standby Diesels
Firewater
Shutdown Cooling
Inert Gas
Steam GenerationTurbine Building
TI Power Distribution Center
Energy Storage Tanks
Demin Water
Salt Piping
336 - 550 MWe net max output2.8+ GWhe energy storage40-41% net thermal efficiency~44 acres Total Site Acreage~16 acres Nuclear Island Site Acreage
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Heat Transport ArchitectureIt’s all about the tanks.
Commercial Constructor Scope
Power Cycle Loop(Water)
EI Salt System(Nitrate Salt)
Nuclear Constructor Scope
Reactor
Primary Pool (Sodium)
9799218-7b_r0
hot tank
cold tank
NI Control• Cold pump speed• Cold tank level• Cold salt temperature
EI Control• Hot pump speed• Hot tank level• Hot salt temperature
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Hot Tank Cold Tank
CAISO April 9, 2019
ሶ𝑊 = 𝜂𝑐 ሶ𝑄𝑅𝑥
Basic Operation
Charging: Low Price ሶ𝑊𝑇 < 𝜂𝑇 ሶ𝑄𝑅𝑥• Hot salt tank level increases
• Cold salt tank level decreases
Discharging: High Price ሶ𝑊𝑇 > 𝜂𝑇 ሶ𝑄𝑅𝑥• Hot tank salt level decreases
• Cold tank salt level increases
Even: ሶ𝑊𝑇 = 𝜂𝑇 ሶ𝑄𝑅𝑥• Steady holt tank salt level
• Steady cold tank salt level
Low price - sell less, high price – sell more
• Store when renewables producing power (lower prices) and discharge when they are not (higher prices)
• Natrium is different from LWRs because the outlet temperature is high enough to support storage.
• Reactor output is steady … minimize cycling of reactor
• Price following above and below 100% reactor power
Pri
ce
Hour of Day0 5 10 15 20
Power Output(MWe)
Storage Capacity (tank level)
0
400
300
200
100
500
0%
80%
60%
40%
20%
100%
Turbine-Generator
Full Power Turbine Hours =𝜌𝑉𝑤𝑜𝑟𝑘𝑖𝑛𝑔 ℎ𝑜𝑡
𝐶ℎ𝑜𝑡𝑇ℎ𝑜𝑡 − 𝐶𝑐𝑜𝑙𝑑𝑇𝑐𝑜𝑙𝑑
ሶ𝑄𝑇𝜂𝑇
− ሶ𝑄𝑅𝑥
How Energy Storage Works
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Thermal Storage Hot Molten Salt Thermal Storage Tank
Cold Molten Salt Thermal Storage Tank
Thermal Storage
• Number of tanks based on customer’s energy need
• Steam generator trains based on size of turbines
• Turbine size based on customer’s power need
Steam Generator Equipment
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Reactor Aux. Building
Int Sodium Hot Leg
Int Sodium Cold LegReactor
and Core
IAC
Head Access
Area
Refueling Access Area
RAC / Reactor Cavity
Reactor Building
Fuel Handling BuildingRAC Ducts
Used Fuel
Water Pool
Key Technical Features of Natrium Reactor Buildings
Sodium Int loop
Sodium/Salt HXs
Salt Piping to/from
Thermal Storage
System
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Key Technical Features of Reactor Equipment Design
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Reactor Core
Heat ExchangerPump
Core Inlet Plenum
CRDMs
Hot Pool
Cold Pool
Heat Transport
Loop Piping
Guard Vessel
Reactor Vessel
In Vessel Transfer
Machine
• Advanced Fuel System– long lived, once through, lower cost fuel
• Efficient Transport Architecture– Molten Salt Loop transports heat to Energy Island
• Simple Reactor Structures– Safety related / nuclear seismic sub-structures
– Open floor plan: few internal walls
• Compact Reactor Equipment• Pantograph In-Vessel Fuel Handling Machine
• Space efficient internals design for easy fabrication
• Natural Circulation (Air) based safety cooling– RAC simplifies safety analysis & defense
• Local Loop Cooling for Refueling (non safety)– Na to air heat exchangers on Intermediate Loop
CompetitiveClean Energy
Simple Nuclear System• Exceptional heat transfer• Passive air cooling• Low pressure • Optimized layout
Adjacent innovations• Concentrated solar power industry• Tunneling industry… vertical cut• Combined cycle gas turbine industry
Flexible• Dispatchable power• Energy storage… price follow• Integrate with renewables• Process heat
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