IAEA Activities on Nuclear Fuel Cycle

Chaitanyamoy Ganguly Head , Nuclear Fuel Cycle & Materials Section

NEA- NSC Meeting , Paris , 10-12 June 2009

IAEA International Atomic Energy Agency IAEA Programme on Nuclear Fuel Cycle & Materials Technologies

Mission Statement

To facilitate development of nuclear fuel cycle options that are : i) economically viable and make efficient utilization of natural uranium and thorium resources ii) safe and environment-friendly, iii)) proliferation-resistant and iv) sustainable. To promote information exchange on 1. exploration, mining and processing of uranium and thorium 2. design, manufacturing, and performance of nuclear fuels 3. management of spent fuel, including storage & treatment of spent fuel & recycling of plutonium, uranium ,thorium and Minor Actinides (MA: Np,Am & Cm) Through: 1. technical co-operation 2. organizing technical meetings, symposia and coordinated research projects 3. preparation of state -of -the art technical documents 4. maintaining & updating databases on nuclear fuels and fuel cycles

IAEA IAEA Sub-programme 1.2.1 on “Uranium Resources and Production and Databases for the Nuclear Fuel Cycle”

• 1.2.1.1 Updating Uranium Resources, Supply & Demand and Nuclear Fuel Cycle Databases [ Red Book 2009 , UDEPO & NFCIS]

• 1.2.1.2 Supporting Good Practices in Uranium Production [Technical Meetings, Technical Co-operation (TC) projects, Training & Uranium Production Site Appraisal Team (UPSAT) ]

IAEA IAEA Meetings on “Uranium Raw Materials & Production Cycle” in 2008

• 42nd Uranium Group Meeting, 13-17 June 2008, Adelaide, South Australia, Australia • Technical Meeting on “Implementing the Best Practices in Uranium Mining, Milling and Production”, 15 – 17 October 2008, Vienna, • Technical Meeting on “Uranium Exploration, Mining, Production, Mine Remediation including Environmental Issues”, 17 - 21 November 2008, Amman, Jordan • Technical Co-operation Workshop on Uranium Exploration, Mining, Production, Mine Remediation including Environmental Issues, 24 - 28 November, Salvador, Brazil

IAEA IAEA Meetings on “ Uranium Raw Materials and Production Cycle planned in 2009

• 43rd Uranium Group Meeting, 17 - 19 June 2009, Vienna,

• Symposium on URANIUM RAW MATERIAL FOR THE NUCLEAR FUEL CYCLE (URAM-2009), 22-26 June 2009, Vienna,

• 44th Uranium Group Meeting, 28 – 30 October 2009, Paris, ( finalizing the draft for Red Book 2009 jointly with OECD- NEA)

• Technical Meeting on Uranium from Unconventional Resources, 3-6 November 2009, Vienna

IAEA IAEA -Technical Cooperation(TC) Projects on Uranium Raw Materials

Country/Region Title of the Technical Cooperation (TC) Projects Argentina Geology Favourability, Production Feasibility and Environmental Impact Assessment of Uranium Deposits to be Exploited using In Situ Leaching Technology Regional Latin Regional Upgrading of Uranium Exploration, Exploitation and America Yellowcake Production Techniques taking Environmental Problems into Account Algeria Contribution to the development of activities for the processing of Algerian ores and purification of uranium concentrates Brazil Practical guidance tools for nuclear safety analysis of remediation and decommissioning actions of the first uranium ore mining and milling facility in Brazil China Techniques And Methods For Optimization Of Uranium Exploration in Both Sedimentary and Volcanic Basins China Integrated Assistance to Institutions Supporting Nuclear Power Programme IAEA Technical cooperation projects..contd

Country/Region Title of the Technical Cooperation Project New Egypt Evaluation of some selected uranium resources in Egypt and production and purification of the yellow cake Jordan Uranium exploration Jordan Uranium extraction from rock phosphate Regional Africa Strengthening regional capabilities for uranium mining, milling and regulation of related activities Venezuela Exploración de los recursos uraníferos de Venezuela

IAEA IAEA Activities Planned for 2010-2011 for the Subprogram on Uranium Raw Materials

• Red Book 2009 : publication in June 2010(NEA), Red Book 2011: finalization of draft in collaboration with NEA • Red Book Retrospective – Country Reports • Update database on World Uranium Deposits (UDEPO) • Database on World Thorium Deposits ( TDEPO) • Technical Document on “Analysis of Uranium Supply to 2060” • Technical Document on “In-Situ Leach (ISL) Mining” • Technical Document on “Economics of Uranium Production Cycle (UPC)” • Technical Document on “Good practice in UPC” in collaboration with World Nuclear Association (WNA). • Technical Co-operation (TC) Projects (9 TC Projects)

IAEA IAEA Databases Related to the Nuclear Fuel Cycle

http://www-nfcis.iaea.org

Information • Navigation through Sources facilities/deposits/records • Member States • Search capabilities (Contact Points) • Consultants • Summary reports for country specific • IAEA Meetings or worldwide • Reliable • Country nuclear fuel cycle profiles Publications • Long term nuclear fuel cycle requirements for different scenarios Inputs • Nuclear power projections NFCIS : Nuclear Fuel Cycle Information System • Nuclear fuel UDEPO : World Distribution of Uranium Deposits cycle options • Reactor physics PIE : Post Irradiation Examination Facilities Database calculations NFCSS : Nuclear Fuel Cycle Simulation System MADB : Minor Actinide Property Database IAEA NFCIS PIE • Nuclear Fuel Cycle Information www-nfcis.iaea.org System • Post Irradiation Examination • Directory of Civilian Nuclear Fuel Facilities Database Cycle Facilities Worldwide • Catalogue of PIE facilities • Facilities from under planning worldwide stage to the decommissioned stage • General information about the • Facilities from uranium milling to facilities reprocessing, spent fuel storage • Technical capabilities of the and heavy water production facilities • Available online since 2001 • Available online since 2004 • 689 facilities in 55 countries • 45 facilities in 21 countries (Apr 2009) (Apr 2009) • TECDOC published in 2009 (TECDOC-1613) MADB NFCSS (formerly • Minor Actinide Property Database VISTA) UDEPO • Bibliographical database on • Nuclear Fuel Cycle Simulation physico-chemical properties of • World Distribution of Uranium System materials containing minor Deposits • Scenario based simulation system actinides • Technical and geological • Carbides, Nitrides, Alloys, Oxides, • Estimates nuclear fuel cycle information on uranium deposits material and service requirements Halides, Elements and other forms • Country level maps of the deposits are covered • Calculates spent fuel arisings and will be displayed on the web site actinide contents • More than 1000 data records from • Available online since 2004 159 publications (Apr 2009) • TECDOC Published in 2007 • Currently 1107 deposits in 67 (TECDOC-1535) • Online since May 2009 countries (Apr 2009) • The simple web version is online • TECDOC to be published in 2009 since 2005 IAEA Properties of LMFR fuel and • Full web version is available since June 2008. ThDEPO to be started fuel assembly structurals. IAEA Sub-programme 1.2.2 (B.2) Nuclear Power Reactor Fuel Engineering

Projects 2008-2009 1. Supporting the sharing of experience in the development and use of fuel structural materials and coolant chemistry management in water cooled nuclear power reactors

2. Promoting good fuel performance and operating practice for current fuel types in water cooled nuclear power reactors

3. Promoting best practices in fuel design and manufacturing and the implementation of new fuel types for water cooled nuclear power reactors Projects 2010-2011 1. Nuclear power reactor fuel R&D, Design and Manufacturing 2. In-reactor behaviour and operational experience of fuel for nuclear power reactors

Collaboration : NE-NP, NA, NS , NEA/OECD, ICTP

Activities : TWGFPT (annual), TMs (1-3 per year), Expert Reviews (2), CRPs (4), Conferences &Workshops (2-4), Monographs & Databases (2)

IAEA IAEA Co- ordinated Research Project “FUWAC”

FUel performance at high burnup and in ageing plant by Management and Optimisation of primary coolant WAter Chemistry (FUWAC)

The CRP started in July 2006, First Research Co-ordination Meeting (RCM), 3-7 July 2006 Second RCM : Chennai, India in December 2007 Third & final RCM : Turku , Finland, 15-18,Sept. , 2009

There are 16 participants from 15 countries, including 5 from WWER countries and 3 from PHWR countries

IAEA Overall objectives of FUWAC

The main objectives include monitoring, maintaining and optimising the water chemistry regime in the primary circuit of water-cooled power reactors, taking into account high burnup operation, mixed cores and plant aging. The main research objective is to understand the causal mechanisms for the following issues:

• Composition & Thickness of Deposit on the Fuel; • Crud Induced Power Shift (CIPS) and Power Limitation; • Fuel Oxide Growth and Thickness; • Corrosion Related Fuel Failure; • Crud Induced Localized Corrosion (CILC); • Radioactivity Build-up in RCS. IAEA Water cooled Power Reactor Fuel Performance Modelling

CRPs DCOM 1981-1985 FUel performance Modelling at Extended Burn Up (FUMEX) FUMEX-I 1993-1996 FUMEX-II 2001-2005 FUMEX-III Started in Dec.2008

Technical Meetings

Fuel modelling, Kendal, 2005 High burnup and economics, Sofia, 2006 PHWR fuel modelling, Mumbai, 2006 PIE, Argentina, 2006 Fuel rod instrumentation, Halden, 2007

IAEA FUMEX-III ( December 2008 onwards )

Purpose The major objective of the CRP is to improve the predictive capabilities of codes used in fuel behaviour modelling for extended burn-up. The focus is on the topics: • Fission gas release • Transient analysis • Pellet to clad interaction (PCI) at extended burn-up above 50 MWd/kg.

IAEA Topics addressed in FUMEX-3

•PCI; PCMI •Transients •High burnup fgr •MOX •Advanced fuels and materials •RIA/LOCA

IAEA Co-ordinated Research Projects (CRs) on Delayed Hydride Cracking (DHC) & Modelling & Simulation of Radiation Effect (SMoRE)

6 DHC 5 SMoRE CANDU RX094 4 RBMK TMT-1 3 India 100-2-3 1000

ln V/CDFt ln 2 CANDU 429 1 0 0 500 1000 Yield stress MPa 750 Fusion INSTITUTE COUNTRY REACTOR TYPE HTR Materials Materials DEMO CNEA Argentina CANDU, PHWR

TOMARI Canada CANDU 500 ITER Consulting Fast Reactor

IPEN Brazil PWR (°C) temperature Operating Thermal Reactor Materials BARC India CANDU Materials 250 KAERI ROK CANDU, PWR 0.1 1 10 100 1000 LEI Lithuania RBMK Radiation dose (dpa) PINSTECH Pakistan CANDU SCK.CEN (Belgium), CEA, EdF (France), INR Romania CANDU BARC (India), JRC (EC), IAE (Poland), IPPE, KI (Russia), KAERI (RoK), MU/INF (Spain), VNINM Russia RBMK, WWER PSI (Switzerland), BU (Slovakia), STUDSVIK Sweden BWR, PWR, surv. on RBMK KIPT (Ukraine), LLNL (USA+), NEA/OECD, Japan-? IAEA IAEA Monograph on Zirconium for Nuclear Applications:

- A reference manual , a state- of- the art review.

- 9 experts from 7 countries are contributing

- Chapters on extraction, alloys, forming, properties and irradiation experience.

Publication in 2009.

IAEA Status of the IAEA Monograph on Zirconium for Nuclear Application :

Forward (C Coleman) (written) Introduction (C Coleman) Completed 1. Alloys (A Nikulina; C Toffolon) Completed 2. Extraction and melting (A Saibaba; Completed R Graham) 3. Fabrication (R Graham) Completed 4. Deformation and texture Completed (E Tenckhoff) 5. Corrosion and hydrogen pickup (part reviewed, work (B Cox) needed) 6. Irradiation damage (C Lemaignan) Completed 7. Irradiation deformation (J Harbottle) Completed 8. Fracture (C Coleman) (Input from 5 required, majority completed) 9. Summary (written) Appendix: Physical properties (written) IAEA Essays on Zr isotopes, fretting and internal friction will be included with the physical properties. Expert Review on Fuel Failures in Water cooled nuclear power reactors

NE Series Document “Review of fuel failures in water cooled reactors (1994–2006)” Expert Group: • D. Dangouleme (EdF, France) • A.Kucuk (EPRI, USA) • K. Kamimura (JNES, Japan) • V. Novikov (VNIINM, Russia) • V. Onufriev (free-lance consultant, Austria) • IAEA staff - V. Inozemtsev and J. Killeen

IAEA Fuel Failures Review: completeness of datasets

Data collected cover 94%of all WR‟s (PWRs, BWRs, WWERs, CANDUs/PHWRs) units operated in 1994-2006. Not covered-Taiwan (not IAEA member), China-6 from 9 units, Mexico-2 units, the Netherlands-1 unit, Pakistan-1 unit, S. Africa-2 units, Slovenia-1 unit. Regarding reactor years operation, data collected cover 99% for PWRs (only data for Quinshan-1 unit for 2002-2006 are missing), 100% for BWRs, CANDU/PHWRs, WWER-1000s and WWER/440/213s, and 80% for WWER/230s (data for Armenia-2, Kola-2, Novovoronez-3,4 are missing for 1994- 96 and 2002-06).

IAEA Fuel Failures Review: Contents

1 INTRODUCTION 5. MECHANISMS AND ROOT CAUSES OF FUEL 2 EVOLUTION OF FUEL OPERATING ENVIRONMENT AND FAILURE DESIGN FUEL CHANGES 5.1 INTRODUCTION 2.1 EVOLUTION OF FUEL OPERATING ENVIRONMENT 5.2 GRID-TO-ROD FRETTING 2.2 FUEL DESIGN EVOLUTION 5.3 FRETTING BY DEBRIS 2.3 FUEL TYPES IN OPERATION 5.4 CORROSION 3 WORLD OVERVIEW ON FUEL FAILURES IN 1994-2006 5.5 PCI (PELLET-CLADDING INTERACTION) 3.1 INTRODUCTION 5.6 MANUFACTURING DEFECTS 3.2 COOLANT ACTIVITY LEVELS 5.7 CROSS FLOW/BAFFLE JETTING 3.3 METHODOLOGY OF FUEL FAILURE RATE EVALUATION 5.8 PRIMARY HYDRIDING 3.4 COLLECTION AND TREATMENT OF FUEL FAILURE DATA 5.9 DELAYED HYDRIDE CRACKING (DHC) 3.5 EVALUATION OF PWR FUEL LEAKERS 6 FUEL STRUCTURAL DAMAGE AND OTHER FUEL 3.6 EVALUATION OF BWR FUEL LEAKERS ASSEMBLY ISSUES 3.7 EVALUATION OF WWER FUEL LEAK RATE 6.1 ASSEMBLY BOW 3.8 EVALUATION OF FUEL LEAKAGE IN CANDU/PHWR 6.2 MECHANICAL DAMAGE DURING HANDLING 3.9 MULTIPLE FAILURE INCIDENTS/DEFECT EXCURSIONS 6.3 CRUD & AXIAL OFFSET ANOMALIES (AOA) 3.10 FUEL ROD FAILURE RATES AND FUEL FAILURE CAUSES 6.4 OTHER MISCELLANEOUS DAMAGES DURING 1987-2006 7 SECONDARY FUEL FAILURES 3.11 EVALUATION OF WORLD AVERAGE LWR FUEL FAILURE 7.1 BACKGROUND RATES 7.2 OBSERVATIONS FROM EXPERIENCES 3.12 CONCLUDING REMARKS ON CHAPTER 3 7.3 DEGRADATION CHARACTERISTICS 4 DETECTION, EXAMINATION AND ANALYSIS OF FUEL 7.4 MECHANISMS FAILURES 8 FUEL FAILURE PREVENTION AND MANAGEMENT 4.1 INTRODUCTION IN PLANT OPERATION 4.2 EVALUATION OF COOLANT ACTIVITY 8.1 EXISTING OPERATING LIMITS AND RECOMMENDED 4.3 LOCALIZATION OF FUEL FAILURES PRACTICES 4.4 FUEL EXAMINATION 8.2 IMPROVEMENT OF QUALITY DURING 4.5 FUEL FAILURE ANALYSIS MANUFACTURING IAEA 9 CONCLUSIONS IAEA Subprogram 1.2.3 on “Management of Spent Fuel from Power Reactor”

• Promoting Strategies for Spent Fuel Management

Objective: To improve the capability of interested Member States to plan and implement improved spent fuel management strategies by identifying problems and fostering collaboration and using information provided by the Agency. • Providing Technical Guidance on Good Practices for Long –term Management of Spent Fuel

Objective: To improve capability of interested Member States to develop individually, or through international co-operation methods for long term management of spent fuel.

IAEA Departments in the IAEA dealing with Spent Fuel Management

Department of Nuclear Energy 1. Nuclear Fuel Cycle and Waste Technology Division (NEFW) 1.2. Nuclear Fuel Cycle and Materials Section

Department of Nuclear Safety and Security

IAEA Spent fuel inventories and accumulation

Cumulative Spent Fuel Arising, Storage and Reprocessing, 1990-2020

SF Discharged

1000 1000 tones HM 500 SF Stored 450 SF Reprocessed 400

350 300

250

200

150

100

50 0 1990 1995 2000 2005 2010 2015 2020

Year

IAEA IAEA activities in 2008/2009 on “Management of Spent Fuel from Power

• Co-ordinated Research Project (CRP) on “Spent fuel Performance Assessment and Research” (SPAR) SPAR II completed ( draft of TECDOC finalized) SPAR III will start in December 2009,

• Workshop on “Burnup Credit Applications” in co-operation with CNS, in Cordoba , Spain in October 2009,

• International Conferences on “Management of Power Reactor Spent Fuel” , Vienna , May 31- June 4, 2010,

• IAEA -TECDOC , “Implications of damaged spent fuel for storage and transport” (in printing), 2009

• IAEA- Technical Meeting in 2008 on “Spent fuel data collection and management for long term storage” (draft of technical document under preparation),

IAEA IAEA activities in 2008/2009 on “Management of Spent Fuel from Power Reactor

• IAEA – Technical Meeting in 2008 on “Storage facility operations and lessons learnt” ( draft of TECDOC under preparation)

• IAEA Technical Meeting on “Potential Spent Fuel Management Interface Issues”, November 2009

• IAEA- TECDOC on “Influence of high burnup and mixed oxide fuel on spent fuel ( final draft under preparation)

• IAEA-TECDOC 1587(2009) on “Spent fuel reprocessing”,

• IAEA- NE Series Document, 2009 on “Costing of Spent Fuel Storage ( in printing),

• IAEA- Technical Meeting on “Regional/multinational spent fuel management facilities”, Vienna, November 2009,

• IAEA- Technical Meeting on “Spent fuel inspections testing and monitoring for storage, Dec. 2009

IAEA IAEA Subprogramme 1.2.4 on “Topical Issues of Nuclear Fuels and Fuel Cycles for Advanced and Innovative Reactors”

1. Liquid Metal-cooled Fast Reactor (LMFR) Fuels & Fuel Cycle Options – multiple recycling of plutonium & burning minor actinides

2. High Temperature Gas-cooled Reactor (HTGR) Fuels & Fuel Cycle Options

3. Small & Medium Size Reactor (SMR) Fuel with long core life

4. Proliferation-Resistant Fuels and Fuel Cycles

5. Thorium Fuel Cycle Options

6. Re-use option of reprocessed uranium

IAEA IAEA activities on Fuels and Fuel Cycle Options for Liquid Metal Cooled Fast Reactor and Closed Fuel Cycle involving multiple recycling of Plutonium and Minor Actinides (MA)

IAEA Nuclear Energy Series Documents on LMFR Fuels and Fuel Cycle

1. Status and trends of sodium cooled fast reactor (SFR) fuels technology; (fabrication, properties and irradiation behaviour of mixed uranium plutonium oxide, mono carbide, mono nitrate and metallic fuels)

2. Back end of fast reactor fuel cycle: Status and perspectives (aqueous and pyro – reprocessing of spent fuel)

3. Status and trends of structural materials for SFR fuel assembly [fabrication, properties and irradiation behaviour of austenitic, ferritic – martensitic and oxide dispersion strengthend (ODS) steel]

IAEA Reuse Options for Reprocessed Uranium

 Dec. 2006 : Working Group was formed  Aug 2007 : Technical Meeting(TM): 50 experts from 14 countries  Feb 2009 : Handbook on Reprocessed Uranium (accepted for publication as a N. E. Series Document)  May 2009 :Proc.of TM accepted for publication as IAEA-TECDOC “Fact-book on High Temperature Gas-cooled Reactor Fuels and Materials”

Develop manuals/handbooks and best practice documents for use in training and education in coated particle fuel technology →Worked together with EC - RAPHAEL EUROCOURSE on „Coated particle fuel‟ Dec 4-7, 2007, NRG, Patten →Final review meeting 3-6 Nov 2008 at Vienna →Document would be published by middle of 2009

IAEA Minor actinide fuel / target will be the critical link between partitioning and transmutation

Process and property of minor actinide compounds and alloys for nuclear fuel and target for incineration in thermal and fast neutron spectra (NE Series Report on Status of minor actinide fuel development : submitted (Apr 2009)

★ MA-fuel fabrication processes: Powder-metallurgy, Injection casting, SOLGEL, Carbothermic reduction, Vibro-pac, Coated particle development, direct coagulation casting, etc., ★ MA-fuels (targets) and fuel types & forms- catalogue (CERMET, CERCER, & METMET, as well as MA-MOX, Coated particle, Metal-alloys & Nitride) ★ Pertinent thermo-physical properties for fuel design, fabrication process and performance Irradiation screening tests, modeling, fuel design and post- irradiation examination

IAEA IAEA Technical Meeting on Country Nuclear Fuel Cycle Profiles December , 2008 , Fukui , Japan

• Discuss „nuclear fuel cycle‟ facilities and policies of Member States (MS)

• Experts from France, Japan, India, Republic of Korea, South Africa and Sweden and GIF participated and a paper was sent from Argentina

• The meeting was open to the public and some 60 delegates from different organizations from Japan participated

Presentation materials and papers are available: http://www.jaea.go.jp/englis h/04/turuga/info/events/081 201iaea/

IAEA INPRO Collaborative Project (Nov. 2007-2010) (Canada , China, ROK, USA &EC)

• Proliferation Resistance: Acquisition/Diversion Pathway Analysis (PRADA) • To improve INPRO methodology in proliferation- resistance • to develop a generic methodology/procedure for the identification and analysis of high- level pathways for the acquisition of weapons usable material from an innovative nuclear system, • to make recommendations on the evaluation indicators and procedure to assess multiplicity and robustness of barriers in an INS against proliferation. …Thank you for your attention IAEA World Distribution of Uranium Deposits (UDEPO)

• Database on Uranium Deposits worldwide ( update: IAEA-TECDOC, 3rd quarter , 2009) • General, Technical and Geological description of the uranium deposits • Data update through consultants • 1107 deposits in 55 countries (March 2009) (data for 234 new deposits incorporated) • Access on the internet with some search and filter capabilities (www-nfcis.iaea.org) IAEA Nuclear Fuel Cycle Information System (NFCIS)

• Directory of Civilian Nuclear Fuel Cycle Facilities Worldwide

• NFCIS update: IAEA-TECDOC-1613 (April 2009) • Uranium milling, conversion, enrichment, fuel fabrication, spent fuel storage, heavy water and zirconium plants. • Annual update through questionnaire to officially nominated contact points in member states • 688 facilities in 54 countries (March 2009) (658 facility data is available in web site) • Access on the internet with some search and filter capabilities (www-nfcis.iaea.org)IAEA Minor Actinide Database (MADB)

• It has been published in www-nfcis.iaea.org since May 2009

IAEA Nuclear Fuel Cycle Information System (NFCIS)

• TECDOC has been published as TECDOC-1613 in April 2009

IAEA Post Irradiation Examination Facilities Database (PIE)

• Data is being updated through contact points in PIE facilities • 39 facilities in 20 countries (March 2009) (Data for additional 7 facilities is in review) • Access on the internet with some search and filter capabilities (www-nfcis.iaea.org)

IAEA Minor Actinide Database (MADB)

• Bibliographic database on thermodynamic and thermomechanical properties of selected compounds and alloys of minor actinides • Materials groups covered: Alloys, Carbides, Carbonitrides, Elements, Halides, Molybdates, Nitrides, Oxides, Tungstates • Minor Actinides covered: Np, Am, Cm • It will be published in www- nfcis.iaea.org in May 2009

IAEA Nuclear Fuel Cycle Simulation System (NFCSS, former VISTA)

• Scenario based simulation system for the estimation of long-term fuel cycle material and service requirements • Capable of calculating actinide accumulations • Database for the historical data • Full Web version is operational (www-nfcis.iaea.org)

IAEA Nuclear Energy Series: structure

Nuclear Energy Basic Principles

General Nuclear Power Nuclear Fuel RW Mgmt Cycle Decomm

Management Technology Resources RW management Systems Development

Human Design of NPPs Fuel Decomm. of Resources Engineering nuclear facilities

Nucl. Operation of Spent Fuel Site Infrastr/Planning NPPs Management Remediation

Economics Non Electrical Advanced Fuel Applications Cycles

Energy System Research Research Analysis Reactors Reactors NFC

Knowledge Management IAEA Nuclear Energy Series

Level 1 Basic Principles (done) and Objectives (2009-2010)

Level 2 Guidelines (fuel QA, 2009-2010)

Level 3 Technical Reports

IAEA FUWAC CRP Team Project

INR, Romania Corrosion and analysis of crud samples in CANDU Zr-4. Characterisation of deposits and oxidation rates

Studsvik, Sweden Characterisation of crud from different PWR operating conditions. Statistical analysis of crud formation. Autoclave testing.

University of New Brunswick, Corrosion (crud) transport in PWR coolants. Zinc addition, boron Canada hide out and CIPS

Saitama Institute of Crud deposition and boiling conditions, heat transfer effects. Local Technology, Japan pH effects. Evaluation of corrosive species in water.

EdF, France Analysis of crud data from 58 PWR plant. Investigation of parameters; eg chemistry, operation, activity build up, different circuit materials, zinc addition.

VTT Finland Effect of alloy composition and water chemistry on corrosion of Zr. Detailed analysis of corrosion layers

VNIPIET, Russian Federation Erosion-corrosion, crud transfer and deposition in WWER. Influence of crud on fuel performance

IAEA FUWAC CRP Team Project

GE USA Advances in water chemistry for simultaneous stress corrosion crack mitigation and dose rate reduction in boiling water reactors (BWRs)

BARC, India Identification of the nature of the deposit, conditions desirable for the deposit formation in the core and possible methods of their removal by decontamination. Varied Chemistry domain (pH and ECP) TiO2 as additive Noble metal chemical addition (NMCA) Additives for MIP (Zn, Ni, Cr, Mg, Mn)

Paks, Hungary Characterisation of crud particles, determination of transport processes, “hot” particles, monitoring of corrosion state of fuel assemblies, fuel cladding behaviour (function of burnup, type of fuel assembly water regime during operation), crud deposition on fuel, application and optimisation of advanced water chemistry "tools" and technologies to influence erosion-corrosion, crud transfer and deposition, improvement of plant chemistry and corrosion diagnostic.

CIAE, China Influence of water chemistry with high lithium on fuel crud buildup

IAEA FUWAC CRP

Team Project

INR, Romania Corrosion and analysis of crud samples in CANDU Zr-4. Characterisation of deposits and oxidation rates

Studsvik, Sweden Characterisation of crud from different PWR operating conditions. Statistical analysis of crud formation. Autoclave testing.

University of New Brunswick, Corrosion (crud) transport in PWR coolants. Zinc addition, boron Canada hide out and CIPS

Saitama Institute of Crud deposition and boiling conditions, heat transfer effects. Local Technology, Japan pH effects. Evaluation of corrosive species in water.

EdF, France Analysis of crud data from 58 PWR plant. Investigation of parameters; eg chemistry, operation, activity build up, different circuit materials, zinc addition.

VTT Finland Effect of alloy composition and water chemistry on corrosion of Zr. Detailed analysis of corrosion layers

VNIPIET, Russian Federation Erosion-corrosion, crud transfer and deposition in WWER. Influence of crud on fuel performance

IAEA FUWAC CRP

Team Project

Czech Republic Operational experience of WWER and PWR. Decontamination technology and post decontamination crud behaviour. Eddy current testing

of magnetite crud in loop in LVR-15

Ukraine NPP water chemistry review, data on crud and corrosion. Water chemistry optimisation with different operating modes

Bulgaria NPP data, hideout effects, solubility and migration of corrosion products

Korea Effect of Water Chemistry (pH, H2) on the crud deposition in PWR

Sweden (Forsmark) Axial Offset Anomaly (AOA) PWR Fuel Crud

IAEA