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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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