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CANDU Technology forGeneration III+ and IV Reactors
Basma A. Shalaby
Chief Engineer
AECL
Presented at WiN Global ConferenceWaterloo, Ont.
2006 June 01
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Development of Nuclear PowerPast,Present and FutureDevelopment of Nuclear PowerPast,Present and Future
CommercialPower
Reactors
Early PrototypeReactors
Generation I
- Shippingport- Dresden, Fermi I- Magnox
Generation II
- LWR-PWR,BWR
- CANDU- VVER/RBMK
1950 2000 2005 2010 2020
Generation IV
- HighlyEconomical
- EnhancedSafety
- Minimal
Waste- ProliferationResistant
- ABWR- System 80+
- AP600- EPR
AdvancedLWRs
Generation III
Gen III Gen III+ Gen-IV
Near-TermDeployment
Generation I-IIIEvolutionaryDesigns OfferingImprovedEconomics
Gen IIGen I
20151995
Generation III+- ACR
- AP1000- ESBWR
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Innovation
Years from today
20 30 40 50 60 70
AdvancedCANDU Reactor
CANDU SCWR
CANDU X
Evolution
Produc
t
Gen IICANDU 6
Continually enhance both the
design and applications basedon the CANDU concept
ACRBuilds on the Legacy;
A Step Towards the Future
Gen IV
Gen V
Gen III+
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Advanced CANDU Reactor (ACR)Generation III+ Technology
Current evolution of CANDU
Combines experience of CANDU 6and domestic programs
Utilizes recent Qinshan experience
Two sizes: ACR-700, ACR-1000 ACR-1000 favoured for Ontario &
international markets
Meets latest CNSC & internationallicensing requirements
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ReactorReactor
CANDUCANDU PWRPWR
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CANDUCANDU PWRPWRFuelFuel
enriched uraniumenriched uranium highhigh burnupburnup
long bundles (3.8 metres)long bundles (3.8 metres)
shut down to refuelshut down to refuel
remove defective fuel only whenremove defective fuel only when shut down to refuelshut down to refuel
natural uraniumnatural uranium lowlow burnupburnup
short bundles (0.5 metres)short bundles (0.5 metres)
onon--power refuellingpower refuelling
remove defected fuel duringremove defected fuel duringoperationoperation
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Heat Transport SystemHeat Transport System
PHWR PWR
COMPARISON OF HEAT TRANSPORT SYSTEMS
* SMALL PIPING - LOW STRESSES
* SAFETY RODS IN MODERATOR
* ON-POWER FUELLING
* FULL-PRESSURE RHR LOOPS
* SIMPLE PIPING, LARGE PRESSURE VESSEL
* SIMPLE FUELLING - ONCE PER YEAR
* LARGE REACTIVITY CHANGE IN OPERATION
* ECC NEEDED TO STOP MELTING AFTER LOCA
Headers
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But, Embracing InnovationACR innovations in safety and cost optimisation:
use of slightly-enriched uranium (SEU) improved core characteristics
use of light water as reactor coolant
plant arrangement optimised higher thermal efficiency
smaller reactor core
advanced construction methods Improved operability and maintainability (O&M)
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ACR Innovations
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Innovation: ConstructabilityConstruction Strategy:
Prefabrication Modularization
Very Heavy Lift Crane (VHL)
Open Top construction
Parallel Construction
Advanced engineering tools Construction time reduced
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Innovation: Safety Two shutdown systems
Two stage Emergency CoreCooling System:
Initial injection from pressurizedtanks in containment
Long term pumped recovery Pumps and heat exchangers act as
dual trains of maintenance cooling
Elevated Reserve Water Tankpassively supplies make-up water
Moderator system acts as a long-term emergency heat sink for
LOCA with loss of ECC
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Innovation: Fuel
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Innovation: CANFLEX Fuel Bundle ACR CANFLEX fuel bundle:
43-element assembly
23 kg
100 mm diameter
500 mm long
43 fuel rods in each bundle:
SEU in 42 rods, in the form of UO2pellets
NU + Dysprosium in central rod
Three times current NU burnup
Spent fuel reduced
Bundle design proof-tested inCANDU 6 reactors
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Materials Innovation: Alloy ControlDeuterium Pickup (mg/dm) vs C & Fe content (ppm wt)
Deuterium pickup (mg/dm)
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Innovation: Smart Systems
Advanced control roomtechnology and alarm
monitoring capability
Advanced plant performancemonitoring and diagnostic
capability: CHEMAND,THERMAND
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Improvements in Operability &
Maintainability ACR design builds on CANDU on-line refuelling capability to offer
unequalled operability.
3 year interval between outages. Short standard outage duration 21 days.
Maximized on-power maintenance.
Redundant heat sink trains as heat sinks. improves outage management flexibility and enables easier steam
generator inspections).
Faster in-core component inspection.
Improvement in removal of Guaranteed Shutdown State (GSS) Automated startup testing.
ACR PSA will incorporate the 3 year schedule. Any constraintsidentified will be designed out.
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Reducing Forced Outage Frequency Eliminating running failures of essential equipment
System/equipment health monitoring: on-line data, readilyaccessible to all for trend analysis
Design and operation connected via Reliability CentredMaintenance ( proven from application to existing CANDUs)
Eliminating Operator Error
Improved Control Room Design
Comprehensive plant status available via large-screen display
Improved alarm recognition system
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ACR-1000 Integrated 2-Unit Plant
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SCWR: Generation IV TechnologySCWR: Generation IV Technology
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CANDU SCWR Generation IV technology
Builds on ACR platform Direct Cycle
Supercritical water
Outlet temperature 650oC
Thermal cycle efficiency 45+%
Operating pressure 25 MPa
T1,
P1
T2,P2
T3,P3
T1,
P1
T2,P2
T3,
P3
T1,
P1
T2,P2
T3,
P3
H.P.TURBINE
S
CONDENSER
Brine
H.P.TURBINE
S
CONDENSER
H.P.TURBINE
S
CONDENSER
Brine
Heat for Co-Generation orIP/LP Turbines
TurbineCompressor
GeneratorCore
Heat for Co-Generation orIP/LP Turbines
TurbineCompressor
GeneratorCore
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SCWR R&DID Task Name1 SUPERCRITICAL-WATER COOLED REACTOR SYSTEM2 Fuels & Materials
3 Mechanical properties (unirradiated)
4 Core structural material down-selection decision (SC 2)
5 Corrosion/SCC (out of pile)
6 irradiate samples HFIR
7 proton irradiation expts8 In-pile loop construction
9 Radiolysis and water chemistry (beam ports/accelerators)
10 Irradiation tests (capsule/accelerator/PIE)
11 Core structural material selection for POAK (SC 3)
12 In-pile water chem/corrosion/SCC and PIE
13 Adequacy of fuel/cladding decision
14 Mechanical properties (irradiated and PIE)
15 Reactor Systems16 Heat transfer in rod bundles
17 freon tests
18 CO2 loop
19 modify codes
20 SCW loop
21 Safety
22 Safety approach specification
23 Safety approach specification decision SC 1)
24 Critical flow (out of pile, sep. effects measurements)
25 LOCA experiments
26 Cladding ballooning (out-of-pile experiments)
27 Out-of-pile instability experiments
28 Instability analysis and data verification
29 Severe accident behavior
30 Design & Integration
35 Analysis tools
36 Prototype Fueled Loop
37 Demonstration Unit (POAK), design only
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2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018
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SCWR R&DR&D issues associated with the SCWR are:
Safety and Design Evaluation
Extension of methods to higher pressures
Scoping evaluations of systems safety Core layout and conditions
Fuels and Materials
Choice of corrosion resistant materials for systems and cladding
Radiolysis and water chemistry studies Facilities and data
Irradiation facilities
Corrosion and heat transfer loop(s)
In-pile test loop(s)
Cogeneration and crosscuts
Hydrogen generation options
Economics and layout of conceptual designs
Fuel cycle options evaluation
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Key R&DHigh Efficiency Channel
High Efficiency Channel (HEC).
Internal insulation (eliminates
CT and annulus gas system). Allows the use of passive
moderator cooling under normaland upset conditions.
Potential walk-away safetywhen combined with Passivemoderator cooling.
Pressure Tube
Porous Insulator
Liner
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Generation VCANDU X Generation V technology
50+ years into the future Ultimate design target
Encourages free thinking and further design innovation
Long-term and speculative R&D Temperature and materials limits for pressure tube reactors
Further extension of fuel channel life
Entirely passive heat removal modes
Self-sustaining fuel cycles (e.g., thorium)
Advanced high temperature systems
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Summary
ACRGeneration III+ technology Generic ACR technology applied to ACR-700 and ACR-1000
family
Includes improvements and innovations in design, safety,
operations, constructability, enabling high availability and shorteroutage periods.
SCWRGeneration IV; 20-25 years development:
multiple use higher temperatures
enhanced efficiency
lower cost
CANDU XGeneration V; 50 years into the future All driven by focused R&D
Technology relevant now & in the future
Builds on proven technology and successful safety performancerecord.
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