Overview of IAEAs Activities in Technology Development for WaterCooled Reactors

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Overview of IAEAs Activities in
Technology Development for Water-Cooled Reactors

• John CLEVELAND, Head
• Water Cooled Reactors Unit
• Nuclear Power Technology Development Section
• Division of Nuclear Power
• IAEA

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Outline

• The IAEA at a glance
• Framework for IAEAs Activities in Technology
  Development for Water-cooled Reactors (LWRs and
  HWRs)
• Some Recent Accomplishments and Current Activities

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The IAEA at a glance

• Established in 1957 as world's "Atoms for Peace"
  organization in the UN family
• 138 Member States
• Worlds center for cooperation on safe, secure
  and peaceful uses of nuclear technologies
• Director General Mohamed ElBaradei
• 2247 staff
• 268 M Regular Budget 51 M
  Extra-budgetary 75 M Technical
  Cooperation

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IAEA Departmental Organization
Director General
DIRECTOR GENERAL
Department of Management
Department of Nuclear Energy
DEPARTMENT OF NUCLEAR ENERGY
Department of Nuclear Safety and Security
Planning and Economic Studies Section
INIS Section
Department of Technical Cooperation
IAEA Library
Department of Nuclear Science and Application
Department of Safeguards
Division of Nuclear Fuel Cycle and Waste
Technology
Division of Nuclear Power
DIVISION OF NUCLEAR POWER
Nuclear Fuel Cycle and Materials Section
Waste Technology Section
Nuclear Power Technology Development Section
Nuclear Power Engineering Section
Nuclear Power Engineering Section
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The IAEA works with its 138 Member States to
promote safe, secure and peaceful nuclear
technologies

• The STATUTE authorizes the agency, inter alia, to
• encourage and assist research on, and
  development and practical application of, atomic
  energy for peaceful uses throughout the world
  and
• foster the exchange of scientific and technical
  information on peaceful uses of atomic energy
• encourage the exchange of training of scientists
  and experts in the field of peaceful uses of
  atomic energy

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PROJECT ON ADVANCED TECHNOLOGIES FOR LWRs AND HWRs

• Conducted in Division of Nuclear Power
• Objective to foster collaboration among Member
  States on advances in technology for improving
  economics and safety
• Implemented with advice and support from the
  Technical Working Groups on Advanced Technologies
  for LWRs and HWR
• TWG-LWR 17 Member States with LWR development
  programmes the OECD-NEA and the European
  Commission
• TWG-HWR 8 Member States with HWR programmes
• Member States TWG Representatives
• Exchange information on national programmes
• Identify areas for collaboration
• Identify national experts for agreed activities
• Review progress and support collaboration on
  agreed activities

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PROJECT ON ADVANCED TECHNOLOGIES FOR LWRs AND HWRs

• TWG-LWR Argentina, Belgium, China, Czech Rep.,
  Finland, France, Germany, India, Italy, Japan,
  Rep. of Korea, Russia, Spain, Sweden,
  Switzerland, United Kingdom, United States of
  America the OECD-NEA and the European
  Commission
• TWG-HWR Argentina, Canada, China, India, Rep. of
  Korea, Pakistan, Romania, Russia
• IAEA tools for collaboration
• Information exchange meetings (Technical
  Meetings)
• Coordinated Research Projects
• Collaborative assessments
• Activities of interest to both TWGs are conducted
  jointly

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Activities focus on improving economics of
advanced designs

• Advanced designs
• Evolutionary designs - achieve improvements over
  existing designs through small to moderate
  modifications
• Innovative designs - incorporate radical
  conceptual changes and may require a prototype or
  demonstration plant

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• SOME RECENT ACCOMPLISHMENTS AND CURRENT ACTIVITIES

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Status of Advanced LWR Designs

• Nuclear power status and projections
• LWR development goals and safety objectives
• Descriptions of 34 advanced PWRs, BWRs and WWERs
• evolutionary and innovative
• electricity or co-generation
• for each nuclear system power conversion
  system IC system electrical system safety
  concept summary level technical data measures
  to enhance economy and reliability

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TECDOC - Status of Advanced LWR Designs 2004
Large Size (above 700 MWe) ABWR and ABWR-II
(GE,Hitachi and Toshiba) APWR and APWR
(Mitsubishi and Westinghouse) BWR 90
(Westinghouse Atom) EPR (Framatome ANP) SWR 1000
(Framatome ANP) ESBWR (GE) KSNP (KHNP) APR-1400
(KHNP) AP-1000 (Westinghouse) EP-1000
(Westinghouse/Genesi) WWER-1000
(Atomenergoproject /Gidropress, Russia)
and  WWER-1500 CNP-1000 (CNNC) SCPR (Toshiba,
et. al.) RMWR (JAERI) RBWR (Hitachi)

• Medium size (300-700 MWe)
• AC-600 (CNNC)
• AP-600 (Westinghouse)
• HSBWR (Hitachi)
• HABWR (Hitachi)
• WWER-640 (Atomenergoproject /Gidropress)
• VK-300 (RDIPE)
• IRIS (Westinghouse)
• QS-600 co-generation plant (CNNC)
• PAES-600 with twin VBER-300 units (OKBM)
• NP-300 (Technicatome)
• Small size (below 300 MWe)
• LSBWR (Toshiba)
• CAREM (CNEA/INVAP)
• SMART (KAERI)
• SSBWR (Hitachi)
• IMR (Mitsubishi)
• KLT-40 (OKBM)

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HWRs Status and Projected Development

• History of HWR development
• Describes designs and projected future
  development
• Forms basis for further TWG-HWR work

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Construction and Commissioning Experience

• Reviews methods for completing construction on
  schedule and budget means for achieving short
  commissioning period
• Qinshan III 12 (AECL CANDUs)
• Kashiwazaki-Kariwa 67 (GE, Hitachi Toshiba
  ABWRs)
• Lingau 12 (Framatome PWRs)
• Yonggwang 56 (KHNP KSNPs)
• Tarapur 34 (NPCIL HWRs)

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Thermo-hydraulic Relationships for Advanced
Water-Cooled Reactors

• Critical Heat Flux
• established a lookup table prediction method by
  combining data
• used in RELAP-5, CATHENA, CATHARE
• prediction methods for bundle geometries,
  including WWER fuel elements
• Post CHF Heat Transfer
• data bank and prediction methods
• Pressure Drop
• correlations for single and two-phase pressure
  drop
• also for natural circulation

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Natural Circulation

• Reviewed applications of NC data and methods for
• core decay heat removal
• severe accident mitigation
• Identified further needs for work, e.g.
• Heat transport in pools
• Condensation in presence of non-condensable gases
• etc.
• Formed a basis for the new Co-ordinated Research
  Programme

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Improving Economics and Safety

• Collaborative Assessment
• 11 industrial organizations
• 4 government agencies
• input from the EC, and OECD-NEA
• Focus is on improving economics

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There is a wide range of means which should be
pursued for improving economics for new plants

• Proven means for improving economics 1
• capturing economies-of-scale
• standardization and construction in series
• multiple unit construction at a site
• simplifying plant design, improving plant
  arrangement and use of modelling
• efficient project management
• working closely and cooperatively with regulators
• improving construction methods to shorten
  construction schedule
• application of computer based advanced
  technologies integrated with increased
  modularization and factory fabrication
• efficient operation and maintenance / reducing
  outages
• 1 in 2000 the OECD-NEA published Reduction of
  Capital Costs of NPPs IAEA activities benefit
  from the results, and expand on them by
  addressing recent experience

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There is a wide range of means which should be
pursued for improving economics for new plants

• New Approaches Deserving Further Development
• Improvement of the technology base for
  eliminating over-design
• Development of systems with higher thermal
  efficiency and expanded applications
• Further development of passive safety systems
• Further development of PSA methods and data bases
  to support plant simplification and to support
  establishment of risk-informed regulatory
  requirements for new plants
• Development of highly reliable components and
  systems, including smart (instrumented and
  monitored) components and methods
• in developing countries, furthering self-reliance
  by increasing portion of SSCs fabricated
  domestically
• Establishment of international consensus
  regarding commonly acceptable safety requirements

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IAEA activities on proven means for improving
economics

• capturing economies-of-scale
• Pursued by several design organizations - e.g.
  AP-600 to AP-1000 ABWR to ABWR-II KSNP to
  APR-1400 WWER-1000 to WWER-1500 N4 and KONVOI
  to EPR (see TECDOC-1391)
• standardization and construction in series
• French experience with 58 PWRs at 19 sites
  (TECDOC-1117)
• TEPCOs expectations for cost reduction with ABWR
  series (TECDOC-1290)
• multiple unit construction at a site
• KHNP AECL experience at 4 unit Wolsong site
  (TECDOC-1290)
• simplifying plant design, improving plant
  arrangement and use of modelling
• Approaches by design organizations (TECDOCs 1391
  and 1290)

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IAEA activities on proven means for improving
economics

• efficient project management
• lessons learned by Ontario Hydro (TECDOC-1117)
• recent positive experiences (TECDOC-1390)
• working closely and cooperatively with regulators
• recent positive experiences (TECDOC-1390)
• improving construction methods to shorten
  construction schedule
• Techniques used at K-6 7 Qinshan III 12
  Lingau 12 Yonggwang 56 Tarapur 34
  (TECDOC-1390 )
• application of computer based advanced
  technologies integrated with increased
  modularization and factory fabrication
• Approaches of AECL and W (TECDOC 1290)
• Techniques used at K-6 7 Qinshan III 12
  Lingau 12 Yonggwang 56 Tarapur 34
  (TECDOC-1390 )
• efficient operation and maintenance / reducing
  outages
• Current CRP on HWR Pressure Tube Inspection
  techniques
• TRS-392 Design Measures to Facilitate
  Safeguards

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IAEA activities on new approaches for improving
economics that deserve further development

• Improving the technology base - through
  improved understanding of T-H phenomena, more
  accurate data-bases and validation of T-H codes
• TECDOC-1149 validation of T-H codes vs.
  experimental data to quantify safety margins
• TECDOC-1203 more accurate relationships for
  CHF, ?P and post CHF h-t assimilated through
  CRP
• TECDOC-1395 validation of HWR codes vs.
  experimental LB-LOCA data to quantify safety
  margins
• CRP on Establishment of a Thermo-Physical
  Properties Data Base
• Validation of HWR codes vs. experimental SB-LOCA
  data (planned)
• CRP on Natural Circulation Phenomena and Passive
  System Reliability
• Course on Natural Circulation in Water Cooled
  Reactors
• Developing systems with higher thermal
  efficiency and expanded applications
• Collaborative assessment on Advanced Applications
  of Water Cooled Reactors
• New CRP on H-T Behaviour and T-H Code Testing for
  SCWRs (in planning)

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IAEA activities on new approaches for improving
economics that deserve further development

• Further development of passive safety systems
• TECDOC-1391 - passive systems are described by
  ALWR design organizations
• CRP on Natural Circulation Phenomena and Passive
  System Reliability
• planned Technical Report Series document on
  Design, Reliability and Cost Considerations of
  Passive Safety Systems in Advanced Water-Cooled
  Reactors
• Further development of PSA methods and data bases
  to support plant simplification and to support
  establishment of risk-informed regulatory
  requirements for new plants
• Activities in IAEAs Division of Nuclear
  Installation Safety
• Development of highly reliable components and
  systems, including smart (instrumented and
  monitored) components and methods
• Addressed briefly in TECDOC 1290
• in developing countries, furthering self-reliance
  by increasing portion of construction and
  component fabrication performed domestically
• Experience at Qinshan III 12 Lingau 12
  Yonggwang 56 (TECDOC-1390 )
• Establishment of international consensus
  regarding commonly acceptable safety requirements
  
• IAEAs Safety Standards Series

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CRP on Natural Circulation Phenomena, Modelling
and Reliability of Passive Systems That Utilize
Natural Circulation 2004-2007

• CNEA, Bariloche, Argentina
• NRI, Czech Republic
• CEA, France
• FZ Rossendorf, Germany
• BARC, India
• Univ. of Pisa, Italy
• ENEA, Italy
• IVS, Slovakia
• JAERI, Japan
• KAERI, Rep. of Korea

• Gidropress, Russian Federation
• University of Valencia, Spain
• PSI, Switzerland
• Idaho State University, USA
• Oregon State University, USA
• Purdue University, USA
• European Commission, JRC - Petten

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CRP on Natural Circulation

• Scope natural circulation for
• core flow
• afterheat removal
• containment cooling
• Objectives
• share experimental data
• investigate phenomena influencing system
  reliability
• examine code and model capabilities
• apply methodologies for determining reliability
  of passive systems
• prepare state-of-the-art report on NC

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CRP on Heat Transfer Behaviour and
Thermo-hydraulics Code Testing for Supercritical
Water cooled Reactors(in planning)

• Suggested by INEL Endorsed by joint session of
  TWG-LWR and TWG-HWR
• Coordination has been agreed with the OECD-NEA
• Included in draft 2006/7 IAEA Programme and
  Budget
• Draft CRP plan has been prepared
• Will be conducted by IAEAs Division of Nuclear
  Power, cooperatively with
• the CRP on Natural Circulation
• IAEAs Division of Nuclear Installation Safety
• Objectives
• to establish a base of accurate data for heat
  transfer to super-critical fluids
• to test computer methods for analyses of SCWR
  thermo-hydraulic behaviour, and to identify code
  development needs

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Summary

• The IAEA provides a forum for international
  collaboration in achieving advances in
  water-cooled reactor technology for improving
  reliability, economics and safety
• Information exchange
• Cooperative research
• Collaborative assessments
• Results are on IAEAs Web Site www.iaea.org
• Worldatom
• Programme - Nuclear Energy
• Advanced Technologies for Light Water Reactors
  (LWRs) and Heavy Water Reactors (HWRs)

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IAEA
atoms for peace