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.1 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved
Introduction to B&W mPower ProgramIAEA Interregional Workshop
Vienna, Austria
July 7, 2011
Doug LeeBabcock & Wilcox Company
.2 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 2
Outline
Introduction
Plant layout
Integral reactor design
Safety concept
Systems
Development testing
Implications from Fukushima
Lead plant deployment
Conclusion
.3 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 3
Alliance between B&W and Bechtel
Risk sharing with 90/10 current ownership
300+ FTE development team
Technology and project execution
Turnkey projects = cost/schedule certainty
Broad industry engagement
Investment from 15 member Consortium
26 member Industry Advisory Council
Goal is to deploy lead plant by 2020
Industry side of public-private partnership
Platform for industry cost/risk sharing
Nebraska Electric G&T Cooperative
Hoosier Energy Rural Electric Cooperative, Inc.
Generation mPower Industry Consortium
Industry Partners
Industry Advisory CouncilIncludes Consortium members above plus:
AEPDayton Power & LightDuke EnergyExelonNPPDVattenfall
Bruce PowerDominionEntergyMidAmericanProgress Energy
www.generationmpower.com
.4 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 4
The Babcock & Wilcox Companyis a leader in clean energy technology and services
for the nuclear and fossil power markets
.4
2010: $2.7B revenue and $5.2B backlog
.5 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 5
Bechtel Power
Over 70 years in the power business
Over 60 years in nuclear power
Over 200,000 MW of completed projects
Nuclear: 74,000 MW
Fossil: 118,000 MW/445 units
Hydro: 26,000 MW/155 units
20012006: 30,200 MW online in 14 countries
20 years of gasification/IGCC experience
28 CT cogen plants, 5,200 MW; 12 solid fuel cogens
Integrated power/desalination; waste-to-energy
Over 15,000 MW of active, new generation power projects
25,000 employees with nuclear experience
2011 Bechtel Power Corporation. All rights reserved.
.6 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 6
Integrated Supply Chain
Multiple sources for forgings and plate
Component fabrication
Mt. Vernon, Indiana
Barberton, Ohio
Cambridge, Ontario, Canada
Fuel fabrication
Lynchburg, Virginia
Control rod drive fabrication
Euclid, Ohio
Critical NSSS Components manufactured in existing B&W facilities
.7 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 7
Goal and Value Proposition
Develop and deploy, by 2020, an SMR that offers:
Lower Capital Cost
Schedule & Cost Certainty
Competitive LCOE Pricing
Within the constraints of:
Proven: GEN III+, established NRC regulation
Safe: Robust margins, passive safety
Practical: Standard fuel, construction and O&M
Benign: Underground, small footprint
.8 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 8
High-Level Requirements 125 MWe Nominal Output per Module and 60-Year Plant Life
NSSS Forging Diameter Allows Readily Available Forgings and Unrestricted Rail Shipment
Passive Safety Requirements Emergency (Diesel) Power Not Required
Minimize Primary Coolant Penetrations, Maximize Elevation of Penetrations Large Reactor Coolant Inventory Low Core Power Density
Standard Fuel (less than 5% U235)
Long Fuel Cycle, 4+ Year Core Life
Spent Fuel Storage on Site for Life of Plant
No Soluble Boron in Primary System for Normal Reactivity Control
Conventional/Off-the-Shelf Balance of Plant Systems and Components
Accommodate Air-Cooled Condensers as well as Water-Cooled Condensers
Flexible Grid Interface (50 Hz or 60 Hz)
Digital Instrumentation and Controls Compliant with NRC Regulations
.9 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 9 .9
Twin-pack mPower plant configuration
40 acre site footprint
Low profile architecture
Water or air cooled condenser
Enhanced security posture
Underground containment
Underground spent fuel pool
Lower overnight construction cost
Competitive levelized cost of electricity 2010 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. Patent Pending
The B&W mPower Nuclear Plant
Security-informed plant design contains O&M costs
.10 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 10
Integral Reactor
Simplified Integrated, Pressurized Water Reactor
Internal Components to Minimize Penetrations
Control Rod Drives No rod ejection
Coolant Pumps Not safety related
Control Rods versus Boron Shim
Load Following Capability Up to 10%/Min
Passive Safety
No safety-related emergency diesel generators
No core uncovery during design basis accident (small break LOCA)
Performance of Critical Functions by Multiple Systems for Improved Reliability and Plant Safety
Multiple Module Plants BOP Equipment Not Shared
.11 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 11
Pressurizer
Steam Generator Tubes
Reactor Coolant
Pumps
Control Rod Drive
Mechanisms
Core
Steam Outlet
Feedwater Inlet
Integral Reactor Arrangement
Primary Loop Secondary Loop
Central Riser
Steam
Feedwater
.12 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 12
Key Features of the Integral RCS
Feature B&W 177 Typical Gen 3 PWR
B&W mPower
Feature B&W 177 Typical Gen 3 PWR
B&W mPower
Rated Core power (MWth) 2568 3415 425
Core average linear heat rate (kWth/m) 18.7 18.7 11.5
Average flow velocity through the core
(m/s)
4.8 4.8 2.5
RCS volume (m3) 325 272 91
RCS volume to power ratio (m3/MWth) 0.14 0.08 0.21
Maximum LOCA area (m2) * 1.3 1.0 0.009
* Assumes double ended break
RCS volume and small break sizes allow simplification of RCS safety systems
Feature B&W 177 Typical Gen 3 PWR
B&W mPower
Rated Core power (MWth) 2568 3415 425
Core average linear heat rate (KWth/m) 18.7 18.7 11.5
Average flow velocity through the core
(m/s)
4.8 4.8 2.5
RCS volume (m3) 325 272 91
RCS volume to power ratio (m3/MWth) 0.14 0.08 0.21
Maximum LOCA area (m2) * 1.3 1.0 0.009
RCS volume/LOCA area ratio (m3 /m2) 250 270 310,000
.13 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 13
Ensure that assemblies are mechanically designed to remain leak tight and maintain structural integrity under all possible conditions
Load enough fuel inventory to accommodate a 4 year operating cycle at a capacity factor of > 95%
Optimize fuel assembly design to maximize fuel utilization
Maintain conservative peaking factors and linear heat rate throughout the operating cycle
Ensure a shutdown margin of > 1% keff/keff under the most reactive conditions and highest worth CRA cluster stuck out
Meet a MDNBR > 1.3 for limiting thermal-hydraulic conditions and confirm via unique CHF correlation
Design Objectives Core and Fuel Assembly
.14 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 14
69 fuel assemblies
< 5 wt% 235U enrichments
No soluble boron for control
Axially graded BPRs
Gd2O3 spiked rods
Control rod sequence exchanges
AIC and B4C control rods
3% shutdown margin
Core Design Features
.15 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 15
Fuel Mechanical Design Features
15
Shortened and Simplified Conventional Fuel Assembly Design
Conventional 17x17 design
Fixed grid structural cage
Design optimized for mPower
Upper End
Fitting
End Grid
Mid Grid
17 x 17 Square Array
Control Rod Guide Tube
End Grid
Lower End Fitting
.16 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 16
Auxiliary Fluid Systems
Reactor Coolant Inventory and Purification (RCIPS) Controls the reactor coolant volume by compensating for coolant contraction or
expansion
Provides hydraulic pressure to CRDM Maintains reactor coolant activity at the desired level by removing corrosion and
fission products
Injects chemicals into the RCS to control coolant chemistry and minimize corrosion
Removes decay heat during normal shutdown and plant cooldown Provides for reactor cavity fill Provides a means for transferring fluids and gases to the radioactive waste
processing system
Provides RCS pressure control by supplying spray flow to the pressurizer
Component Cooling Water Supporting system for RCIPS by transferring heat to the chilled water system
.17 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 17 .17
Low Core Linear Heat Rate Low Power Density Reduces Fuel and Clad Temperatures During
Accidents
Low Power Density Allows Lower Flow Velocities that Minimize Flow Induced Vibration Effects
Large Reactor Coolant System Volume Large RCS Volume Allows More Time for Safety System Response
in the Event of an Accident
More Coolant Is Available During a Small Break LOCA Providing Continuous Cooling to Protect the Core
Small Penetrations at High Elevation High Penetration Locations Increase the Amount of Coolant Left in
the Vessel after a Small Break LOCA
Small Penetrations Reduce Rate of Energy Release to Containment Resulting in Lower Containment Pressures
Inherent Safety Features
CONFIDENTIAL AND PROPRIETARY TO B&W
.18 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 18
ECCS Safety Functions
Passively removes core heat following certain anticipated operational occurrences and analyzed accidents
Passively reduces containment pressure and temperature following certain analyzed accidents
Provides an alternate means of reactivity control for beyond design basis accidents (i.e. ATWS)
Provides a barrier to the release of fission products to the environment
.19 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 19
B&W mPower Containment
Underground containment and fuel storage buildings
Metal containment vessel Environment suitable for human
occupancy during normal
operation
Simultaneous refueling and NSSS equipment inspections
Leakage free Volume sufficient to limit internal
pressure for all design basis
accidents
2010 Babcock & Wilcox Nuclear Energy, Inc., All rights reserved.
.20 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 20
Balance of Plant Design
Plant designed to produce a nominal 125 MWe
Conventional steam cycle equipment (small, easy to maintain and replace)
BOP operation not credited for design basis accidents
Conventional
Air-Cooled Condenser
Steam Cycle
2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.
.21 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 21
State of the art digital system
Provides monitoring, control and protection functions
Separate safety and non-safetysystems
Implement lessons learned fromcurrent licensing activities
Currently developing digitalcontrol system architecture
Instrumentation and Controls
.22 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 22
I&C Philosophy
Highly-Reliable, Integrated and Scalable Digital I&C System
I&C System Must Have Highest Degree of Licensing Certainty
Complies with All Regulatory, URD Requirements
Minimizes Regulatory Challenges with Digital I&CCyber-security, Diversity, Independence
Integrated, Modernized Human-Factored Design
High Level of Plant Automation
Control of Startup, Shutdown, Load Followingsupport staffing plan
Deliver Comprehensive O&M Strategy
Use of commercially-available components
Managed obsolescence
.23 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 23 .23
Component Tests Reactor Coolant Pump CRDM Fuel Mechanical Testing CRDM/Fuel Integrated Test Fuel Critical Heat Flux Emergency High Pressure
Condenser
Integrated Systems Test (IST) Heat Transfer Phenomena Steam Generator Performance LOCA Response Pressurizer Performance Reactor Control
Development Testing Programs
Center for Advanced Engineering
Research (CAER)
Bedford, VA
.24 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 24
Testing Program
Objective Method Location Duration/ Timing
Rx coolant pump performance High temp test loop Curtiss Wright 2011-2016
CRDM performance Bench & autoclave Euclid 2010-2016
Fuel mechanical design Mechanical and cold
flow
Lynchburg 2010-2012
Fuel bundle performance Autoclave Euclid 2012-2013
Integrated CRDM/fuel assembly Autoclave Euclid 2012-2014
DNB correlation CHF testing Stern Lab 2010-2012
Emergency condenser IST & contract TBE 2011-2014
Integral reactor performance IST Lynchburg 2011-2014
.25 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 25 .25
IST Objectives
Integrated system performance
Steam generator and component performance
Computer code validation
Licensing support
Control and protection systems verification
Design enhancements
Simulator development and verification
Operating procedures and training development
Demonstration to potential customers
February 2011A broad spectrum of objectives identified
.26 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 26
IST Features
Scaling
Full height
Full pressure and temperature
Power, area and volume scaled
Real time operation
Trace heating
Systems Simulated
Integral reactor coolant
Steam and feedwater
Reactor coolant inventory and purification
Emergency core cooling
Component cooling water
Protection and control
Integral reactor and important systems carefully designed
.27 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 27
Status
Building complete
Equipment procurement complete
Integral loop assembly in process
Equipment installation in process
Operating and test teams hired
Procedures in preparation
Start-up August-September
Testing will begin this year
.28 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 28
Design Considerations for Fukushima-Type EventsEvents and Threats B&W mPower Reactor Design Features
Earthquakes
And Floods
Seismic attenuation: Deeply embedded reactor building dissipates energy, limits motion
Water-tight : Separated, waterproof reactor compartments address unexpected events
Loss of Offsite Power Passively safe: AC power, offsite or onsite, not required for design basis safety functions
Defense-in-depth: 2 back-up 2.75MWe diesel generators for grid-independent AC power
Station Blackout 3-day batteries: Safety-related DC power supports all accident mitigation for 72 hours
APU back-up: Auxiliary Power Units inside reactor building recharge battery system
Long-duration station keeping: 7+ day battery supply for plant monitoring/control
Emergency
Core Cooling
Gravity, not pumps: Natural circulation decay heat removal; water source in containment
Robust margins: Core power density (11.5kW/m) and small core (425MWth) limit energy
Slow accidents: Maximum break small compared to reactor inventory (4.7x10-5m2/m3)
Containment Integrity
and Ultimate Heat Sink
Passive hydrogen recombiners: Prevention of explosions without need for power supply
Internal cooling source: Ultimate heat sink inside underground shielded reactor building
Extended performance window: Up to 14 days without need for external intervention
Spent Fuel Pool
Integrity and Cooling
Protected structure: Underground, inside auxiliary containment
Large heat sink: 30+ days before boiling and uncovering of fuel with 40 years of spent fuel
Multi-layer defense mitigates extreme beyond-design basis challenges
.29 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 29
Lead Plant
Generation mPower and TVA Letter of Intent
Joint development and pursuit of construction permit and operation license
Up to six B&W mPower reactors at the Clinch River site in Roane County, Tennessee
Deploy first unit by 2020
.30 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 30
Integrated Part 50/52 Lead Plant Deployment ScheduleCY CY CY CY CY CY CY CY CY CY CY
2011 2012 2013 2014 2015 2016 2017 2018 2019 2020 2021
Clinch River Project 10 CFR 50 Process
Submit CPA
NRC CPA Review
CP DSER
CP Issuance
Submit OL Application
NRC Review OL Application
FSER Issued
Fuel Load
COL Issuance
Submit DCA
NRC DCA Review
NRC COLA Review
DC RulemakingFSER IssuedCOLA Submittal
COD
mPower DCD & COLA 10 CFR 52 Process
Pre-op TestingStart-up Testing
Site Prep/Construction/ITAAC/Fuel Load/Startup Testing
Hearing
COD
Site Prep/Construction
OL Issuance
.31 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved 31
Conclusion
B&W and Bechtel have formed an alliance to design and construct turn-key mPower SMR plant
The mPower modular reactor plant has a unique integral reactor design with passive safety system design
Design and licensing activities are well underway
A comprehensive test program is in process
A letter of intent has been signed with TVA for up to six units for deployment of the first unit by 2020