1 babcock & wilcox proprietary information introduction to mpower irug conference salt lake...

.1Babcock & Wilcox Proprietary InformationBabcock & Wilcox Proprietary Information

Introduction to mPowerIRUG Conference

Salt Lake City, UtahJuly 27, 2011

Jason WilliamsBabcock&Wilcox

.2Babcock & Wilcox Proprietary Information

Outline

• Introduction• Plant layout• Integral reactor design• Safety concept• Development testing• Methods Development• Conclusion


Alliance between B&W and Bechtel• Risk sharing with 90/10 current ownership

• 250+ 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

http://www.generationmpower.com/


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

.4

.5Babcock & Wilcox Proprietary Information .5

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

© 2011 The Babcock & Wilcox Company. All rights reserved. 5


“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 costCompetitive 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


Integral Reactor

© 2011 The Babcock & Wilcox Company. All rights reserved.

• 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


Pressurizer

Steam Generator Tubes

Reactor Coolant Pumps (12)

Control Rod Drive Mechanisms (61)

Core(69 Bundles)

Steam Outlet (2)

Feedwater Inlet (2)

Integral Reactor Arrangement

1900 psia, 609°F Core Outlet

568°F Core Inlet

25.4M lbm/hr

Primary Loop

571°F at 825 psia50°F Superheated Steam

325°F Feedwater

Secondary Loop

Central Riser


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


69 fuel assemblies< 5 wt% 235U enrichmentsTwo fuel assembly configurations No soluble boron for controlAxially graded BPRsGd2O3 spiked rodsControl rod sequence exchangesAIC and B4C control rods3% shutdown margin

Core Design Features


Fuel Mechanical Design Features

11

Shortened and Simplified Conventional Fuel Assembly Design

Conventional 17x17 design

Fixed grid structural cage

Design optimized for mPower

© 2010 Babcock & Wilcox Nuclear Power Generation Group, Inc. All rights reserved.

Upper End Fitting

End Grid (Inconel-718)

Mid Grid (Zircaloy-4)

17 x 17 Square Array

Control Rod Guide Tube (Zircaloy-4)

End Grid (Inconel-718)

Lower End Fitting



•

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


Key Features of the Integral RCS

Feature B&W 177 Typical Gen 3 PWR

B&W mPower


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



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


ECCS Safety Functions

• Removes core heat following certain anticipated operational occurrences and analyzed accidents

• 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


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.


• 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


Principal Computer Codes

Current thinking…• RELAP5-3D

Primary T/H system transient response Multi-dimensional hydrodynamics, reactor kinetics Large code assessment database for PWR T/H phenomena

RELAP5-HD (simulator tool from GSE) available for supplemental T/H analysis

• GOTHIC Containment analysis Supplemental T/H system transient response


Evaluation Methodology Development and Assessment Process (EMDAP) (RG 1.203)

Element 1Establish requirements for evaluation model capability

1. Specify analysis purpose, transient class and power plant class2. Specify figures of merit3. Identify systems, components, phases, geometries, fields and processes that should be modeled4. Identify and rank phenomena and processes (PIRT)

Element 2Develop assessment base

5. Specify objectives for assessment base6. Perform scaling analysis and identify similarity criteria7. Identify existing data and/or perform integral (IET) and separate effect tests (SET) to complete database8. Evaluate effects of IET distortions and SET scale up capability9. Determine experimental uncertainties

Element 3Develop evaluation model

10. Establish EM developmental plan11. Establish EM structure12. Develop or incorporate closure models

Element 4Assess evaluation model adequacy

Closure relations (bottom-up)

13. Determine model pedigree and applicability to simulate physical processes14. Prepare input and perform calculations to assess model fidelity and/or accuracy15. Assess scalability of models

Integrated EM (top-down)

16. Determine capability of field equations and numeric solutions to represent processes and phenomena17. Determine applicability of EM to simulate system components18. Prepare input and perform calculations to assess system interactions and global capability19. Assess scalability of integrated calculations and data for distortions

EM Resolution

20. Determine EM bases and uncertainties

Has adequacy standard been

met?

No Yes

Return to appropriateElements, make andAssess corrections

Perform plant eventanalysis


Identify and Rank Phenomena

• Preliminary PIRTs SB LOCA – Ortiz, Ghan, NUREG/CR-5818 Non LOCA – Greene, et al., ICONE 9, 2001 Containment – OECD/NEA CSNI-1999-16

• Final PIRTs SBLOCA – DEGB in mid-flange attached pipe

• Plans Long-term Non LOCA events (±DT, ±Vol, -Flow) Short-term Non LOCA events (reactivity anomalies)


Specify Figures of Merit• Chapter 15 Non LOCAs

DNBR Fuel centerline temperature Primary and Secondary Pressure Mass and Energy releases for Chapter 6 analysis (Steamline break only)

• Chapter 15 LOCA Liquid level, surrogate for peak clad temperature and oxidation-related

measures Mass and Energy releases for Chapter 6 analysis

• Chapter 15 Reactivity initiated events Fuel enthalpy (also feeds into source term assumptions in radiological)

• Chapter 15 Radiological events A person located at any point on the boundary of the exclusion area for any 2-

hour period would not receive a dose in excess of 25 rem A person located at any point on the outer boundary of the low population zone

would not receive a dose in excess of 25 rem• Chapter 6 Containment events

Pressure


Conclusion

• B&W and Bechtel have formed an alliance to design and construct the 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 2012

1 babcock & wilcox proprietary information introduction to mpower irug conference salt lake...

Documents