Attachment 3 CRDM Meeting Slides Non-Proprietary Version · I REACE NO -RPITR VESO *c21 acc&W cxul...
Transcript of Attachment 3 CRDM Meeting Slides Non-Proprietary Version · I REACE NO -RPITR VESO *c21 acc&W cxul...
Attachment 3
CRDM Meeting Slides Non-Proprietary Version
babcock & wilcox nuclear energy, inc.
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nuclear energy
B& W mPower TM Reactor
Control Rod Drive Mechanism Design and TestingMarch 23, 2011 - USNRC, Rockville, MD
I THE BABCOCK & WILCOX COMPANY. ALL RIGHTS RESERVED
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AGENDA
" OBJECTIVES
" INTRODUCTIONS
" REACTOR DESIGN OVERVIEW
• CRDM DESIGN OVERVIEW
" CRDM TESTING PROGRAM
* CONCLUSIONS
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Reactor Design Overview
ýe 2011 B a bcoc'ý& \V I [GO ML]cleai Energ,,, Inc All rights reserved.
Overview of the B&W mPower Reactor Design
High-Level Requirements* 125 MWe plant net output per module & 60-year plant life* NSSS forging diameter allows domestic forgings, unrestricted
rail shipment* Passive safety requirements - emergency (diesel) power is
not required*Minimize primary coolant penetrations, maximize elevation ofpenetrations
* Large reactor coolant inventory
* Low core power density
* Standard fuel (less than 5% enriched U-235)
* Long fuel cycle, 4+ year core life
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High-Level Requirements-Cont.
" Spent fuel storage on site for life of plant
" No soluble boron in primary system for normal reactivitycontrol
" Conventional / off-the-shelf balance of plant systems andcomponents
" Accommodate air-cooled condensers (Baseline) as well aswater-cooled condensers
" Flexible grid interface (50 Hz or 60Hz)
" Digital instrumentation and controls compliant with NRCregulations
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Containment Requirements
Underground containment and fuelstorage buildings
" Favorable seismic response
" Missile protection
" Environment suitable for humanoccupancy during normal operation
" Simultaneous refueling and NSSSequipment inspections
" Volume sufficient to limit internalpressure for all design basis accidents
Site Development
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Technology Overview
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Integral Nuclear Steam Supply System
• Integrates core, steam generator, and pressurizer into asingle vessel
0 Control rod drive mechanisms (CRDMs) and primarycoolant pumps inside vessel
* Reactor coolant pressure boundary penetration size andlocation minimize coolant loss during LOCA - core remainscovered throughout the design basis LOCA
0 Housed within a steel lined, reinforced concrete, drycontainment
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Overall Reactor Arrangement
Pressurizer
Steam Generator Tubes
Steam Outlet
Feedwater Inlet
ReactorCoolant Pumps
Upper Internals withControl Rod DriveMechanisms
Lower Vessel
Core --
Inherent Safety Features
*Large reactor coolant volume* Large RCSvolume
" More coolant to protect the core
* Small penetrations at high elevation" High penetration locations
* Small penetrations
Balance of Plant Design
* Plant designed to produce anominal 125 MWe
• Air-cooled condenser (Baseline)* Water-cooled condenser
* Conventional steam cycleequipment (small, easy tomaintain and replace)
* BOP operation not credited fordesign basis accidentsAll fuel can be cooled for a minimum of 72hours without any BOP system
Air CooledCondense
Generato•
LP turbine
HP turbine-, - CondensatePump
HaFWHeatersFW Pump
ConentonaAi- U-ldCodneB&WmPower Reactor125 MWe Module
Instrumentation and Controls
State of the art digital system
Provides monitoring,control, andprotection functions
Separate safety andnon-safety systems
Implement lessonslearned from currentlicensing activities
Northrop Grumman under contractto develop I&C architecture
Summary" NSSS utilizes an integral PWR design
" Uses a single integral economizer once through steam generator to producesuperheated steam
" Internal reactor coolant pumps and control rod drive mechanisms" Internal pressurizer
* Passive safety systems, inherent NSSS safety features" Long operating cycle
* Underground containment
* Spent fuel storage on site for life of plant
* Reactor plants for multiple module designs
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