CURRENT NUCLEAR PLAN IN ARGENTINA, AND I

1
CAREM Project

• CURRENT NUCLEAR PLAN IN ARGENTINA, AND IC STATUS
  OVERVIEW

Technical Working Group IC Meeting IAEA Viena,
23 27 May 2007
Eng. Ana Fittipaldi Research Reactors Project
Coordinator Nuclear Energy Unit GAEN - CNEA
fittipal_at_cab.cnea.gov.ar
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Presentation structure
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Current Nuclear Plan in Argentina

• In August 2006, the government announced the
  Nuclear Power Plan, and the Nuclear Reactivation
  Activities
• It has two strategic objectives
• Nuclear Power generation for Electricity
  consumption
• Nuclear Technology Applications, for Human Health
  and Industry

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Current Nuclear Plan in Argentina

• The announcement included
• Atucha II
• Finalized Atucha II (Nucleo Eléctrica Argentina
  SA (NASA) is the project leader, with the
  collaboration of the National Atomic Energy
  Commission of Argentina, and other National
  Nuclear Industries
• Civil and Hydraulic work started last year, and
  during this year, it is expected to start with
  the electromechanical mounting of the utility.

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Current Nuclear Plan in Argentina

• Atucha II (Cont.)
• This is a great challenge for the country, not
  only by means of providing energy, but also
  reactivating all Scientifics aspects,
  technologic, and industrial associated to the
  nuclear field, including generating a big demand
  in specialized human resources.

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Current Nuclear Plan in Argentina

• Atucha II (Cont.)
• This utility was started 26 years ago, and still
  is unfinished, but it is planned to be finished
  at the end of 2010 with 745 MWe
• The schedule project has three phases
• Phase 1 Project Reactivation
• Phase 2 Construction and Mounting
• Phase 3 Commissioning and Power start up

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Current Nuclear Plan in Argentina

• CNE (Embalse NPP) life extension
• It was signed last year a contract with AECL
• Feasibility Studies of a Fourth NPP
• It was signed last year a contract with AECL
• The competence of Argentina is clearly proved
  through its nuclear exportation history and the
  most recent example is OPAL Reactor built in
  Australia by INVAP

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Current Nuclear Plan in Argentina

• CAREM 25MWe Reactor
• Own design
• National Atomic Energy Commission of Argentina
  (CNEA), is the project leader
• Brief description later

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History, current status of CAREM Project
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Introduction

• CAREM Project Objectives are

• To develop the first Argentinean Power Reactor

• To enter the future reactors competition from
  the beginning

• To generate development areas for CNEA, its
  associated companies and private industry

• To repeat the success obtained in Research
  Reactors exportation

• To exploit Argentine Nuclear Power Plants

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Introduction previous experience
Argentina
RA3
RA0
Atucha I
Atucha II
Embalse
CAREM
RA1
RA6
RA8
RA2
RA4
1957
1966
1972
1978
1984
1989
1998
2009
1965
1968
1974
1982
1997
2006
20xx
1988
Exported
RP0-Peru
RP10-Peru
NUR-Algeria
ETRR-Egypt
OPAL-Australia
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Introduction

• History

• 1984 Official presentation during the IAEA
  Conference in Lima, Peru
• 1995 Presentation of the Safety Preliminary
  Report to the Nuclear Regulatory Authority
• 1997-1998 Optimization and improvement of
  engineering concept

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Introduction History

• 1999-2004
• Creation of new integrated teams (1999-2001)
• review consolidation of CAREM-25 engineering
  Prototype
• Schedule and execution of pending research
  verification
• Fuel elements pressure drop qualification,
• control rods and safety hydraulics mechanisms
  tests
• Evaluation of CAREM commercial modules
• development of integral optimization design
  methodology,
• first tests and pre dimensioning

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Introduction
CAREM vs. Classic PWR comparison
Pressurizer
Steam Generators
Control Mechanisms
CAREM Integrated Reactor
Main Pumps
Pressure Vessel
Classic Design
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Introducción
Introduction
CAREM Performance
Integrated Hydraulic Control Mechanisms
Self-pressurized
Pressure Vessel
Condensate from Secondary
Vapor to Secondary
Steam Generator
Core
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Introduction
Introducción
Innovative aspects
CONVENCIONAL REACTOR
CAREM
Integrated
Loop
Primary System
No (Self presurized)
Yes
Pressurizer
Primary circulation
Natural
Forced
Hydraulic (internal)
Control Mechanisms
Magnetic (external)
Passive
Active
Safety Systems
Innovative Reactor
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Presentation structure
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Technical Description

• Advanced Reactor of type
• light water
• enriched uranium
• Integrated
• Self-pressurized

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Technical Description
Characteristics

• Power
• prototype 27 MWe
• natural convection
• to 150 MWe
• forced convection
• from 150 MWe to 300 MWe
• Pressure 122.5 atm,
• Temperature 326C
• Intrinsic Safety is a priority by design.

Hydraulic control mechanisms
Reactor pressure vessel
Barrel
Steam Generator
Core
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Technical Description
Core

• Thermal Power 100 MW
• Total Uranium Mass 3812.5 kg

Fuel Rod
Fuel Element

• Equivalent diameter 131 cm
• Number of Fuel Elements 61

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Technical Description Core
Fuel Elements

• Active Length of Fuel Element 140 cm
• Fuel Diameter (UO2) 0.76 cm
• Fuel Rod external Diameter (Zry-4) 0.90 cm
• Pitch between Fuel Rods 1.38 cm

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Technical description
Passive Safety Systems
RHRS
SSS

• Two shutdown systems
• 1. fast rods (FSS)
• 2. Boron injection (SSS)
• Residual Heat Removal System (RHRS) with
  condensers
• Low Pressure Injection System (LPIS) low
  pressure water with accumulators
• 48 hs autonomy (no need of electrical power nor
  operators intervention)

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Technical description
Reactor Auxiliary Building
Transfer Channel
Auxiliary Pool
Fuel Elem. Pool
Control Room
Instrumentation Racks
Compressors Room
Pressure Suppression Pools
Main Entrance
Containment
Lockers
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Presentation structure
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Developments and experimental facilities
Fuel and absorbing rods

• Fuel assembly prototype allowances and
  manufacturing techniques

• High Pressure Loop Endurance test, wear-out and
  fretting

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Developments and experimental facilities

• Low Pressure Loop Hydraulic losses
• Flow vibration

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Developments and experimental facilities

• Critical Heat Flux Tests in fuel bars
  correlations determination

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Developments and experimental facilities
High Pressure and Natural Convection Loop (CAPCN)

• For Primary Circuit Dynamics Tests
• 11 scale in height
• natural convection
• self-pressurized
• Dynamics tests
• Control tests

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Developments and experimental facilities
Hydraulic Mechanisms test circuit
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Developments and experimental facilities
Critical Facility RA-8

• Criticality
• Power distribution
• Calculation chain Validation

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Presentation structure
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Posicionamiento Internacional
Market Study International Situation
Generation Evolution
Enhanced Safety
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Market Study International Situation

• Generation IV
• USDOE Evaluation, approved by the Generation IV
  International Forum (GIF), 2001-2002

Purpose evaluate the feasibility of
technological alternatives of nuclear power
generation to satisfy future demand Evaluation
Committee 100 experts from different countries,
organizations, companies and universities
US-DOE, IAEA, CEA, JAERI, KAERI, AECL, CNEN,
CNEA, EPRI, ANL, INEEL, ORNL, BNFL, Westinghouse,
Framatome, COGEMA, General Atomics, Toshiba,
Exelon, Dominion, Electricite de France,
Masachuset Institute of Technology, etc
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Market Study International Situation
Results of Generation IV

• CAREM was considered a feasible project (among
  other 100)
• Comparison of new designs
• 8 objectives, 15 criteria y 24 indicators
• Results
• Fuel use and waste management reaches the fixed
  standards
• Economy above average
• Safety aspects outstanding

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Market Study International Situation
International Near Term Deployment

• potential to lead the market in the next decades
• same or better performance than current designs
  ALWR
• advanced development
• designers capable to carry out the project
• CAREM competitors (Integrated Primary System
  Reactors)
• IMR
• IRIS
• SMART

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Market Study International Situation
Summary
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Presentation structure
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Current Status
Project Schedule 5 years
3
4
1
2
3
4
5
1
2
5
Tasks
Tasks
1
2
3
4
1
2
3
4
1
2
3
4
1
2
3
4
1
2
3
4
Work
Instrumentation and control
Control
Civil work
Owner expenses
conventional Instrumentation
Machinery and equipment
Nuclear Instrumentation
Turbine
Component production
Pressure vessel
Equipment
Contention
Montage, transport and equipment
Steam generators
Personnel and technical advise
Reactor Internals
Personnel
Coordination
Control system
Electromech. Components
Licensing
Reactor Auxiliaries
Engineering
Electric power
Control
Auxiliary services
Montage Direction
Tertiary
Montage Personnel
Ventilation
Development and experim. Verif.
First core
Preoperational Tests and Start-up
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Presentation structure
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Conclusions

• CAREM design balances
• innovation ? proved technology
• It has become a international referent, which
  will probably lead the future of low and medium
  size power plants.
• CAREM prototype would be Argentine Power Reactors
  base.

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Conclusions
Prototype importance

• Prototype construction will allow the
  appropriation of construction technology of
  nuclear power reactors
• CAREM would generate developments for CNEA, its
  associated companies and private industry
• The technical and commercial benefit obtained
  with CAREM construction will be grater than the
  required investment
• It is a key element for trading the reactor
  abroad

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IC STATUS OVERVIEW

• IC Tasks in ATUCHA II
• to identify the different systems components,
  modules etc. (because due to this long term
  project, might be some loss of components)
• to clarify engineering system designs
• CNEA will perform the nuclear detector
  characterization.

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IC STATUS OVERVIEW

• IC for CAREM Reactor Prototype (25MWe)
• Most of the IC systems are either in a
  Conceptual Engineering design phase, or in a
  Basic Engineering design phase
• A CAREM Reactor simulator is being in a Basic
  Engineering design phase, and might be used to
  test control loops of the Control System, and to
  train operation staff

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IC STATUS OVERVIEW

• IC for CAREM Reactor Prototype (25MWe) (Cont.)
• It is a great challenge to deal with new design
  trends in instrumentation. These new design
  techniques deal with modular systems design,
  which can be adapted (with low costs) to several
  different IC applications in the NPP areas.
• Besides, it is a great challenge for us (the
  designers), and for our Nuclear Regulatory Body
  to license software based systems, and COTS

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IC STATUS OVERVIEW

• IC for CAREM Reactor Prototype (25MWe) (Cont.)
• Since 2005, CNEA has a National Project with
  IAEA regarding to the CAREM Reactor Development
  of High Pressure and High Temperature Test Loop
  For Hydraulic Control Rod Drive Mechanism And
  Instrumentation And Control Systems For The
  Reactor Protection System of CAREM Reactor

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IC STATUS OVERVIEW

• IC for CAREM Reactor Prototype (25MWe) (Cont.)
• One of the main objectives of this project is
• Knowledge preservation and train engineering
  staff in new IC technologies. The acquired
  expertise can be utilized in additional national
  or regional IC projects. These new applications
  require the adaptation of new and innovative
  techniques in system design, verification and
  validation, testing and maintenance.

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IC STATUS OVERVIEW

• General IC Status Overview
• Capability in the Country to manage and develop
  large IC projects like our recent OPAL project
  (2000-2006) that deal with all IC standards for
  NPPs (INVAP was the Project Leader)
• Developed and manufactured nuclear detectors
  (Ionization Chambers, Fission Chamber, Campbell
  Detector, SPNDs, etc) done by CNEA, and their
  corresponding nuclear channel, including Campbell
  Channel done by INVAP

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IC STATUS OVERVIEW

• General IC Status Overview (Cont)
• Capability in the Country to do 1E qualification
  components
• Continue working in reliability studies, and
  common cause failure for digital systems

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IC STATUS OVERVIEW

• General IC Status Overview (Cont)
• Regarding to IC Standards, the following
  standards are applied in IC projects
• Nuclear Regulatory Body of Argentina Standards
  http//www.arn.gov.ar
• IAEA Safety Guides (ej 50 SG D1/50 SG D3)
• International Standards (IEEE, IEC, etc) for
  specific requirements

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CAREM Project

• CURRENT NUCLEAR PLAN IN ARGENTINA, AND IC STATUS
  OVERVIEW

Thank You for Your Attention !!!!!!!!!
Eng. Ana Fittipaldi Research Reactors Project
Coordinator Nuclear Energy Unit GAEN - CNEA
fittipal_at_cab.cnea.gov.ar

• Technical Working Group IC Meeting
• IAEA Viena, 23 27 May 2007