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IAEA IAEA Technical Meeting on Nuclear Fuel Cycle Profiles1-2 December 2008, Fukui, Japan
IAEA Activities on Nuclear Fuel Cycle - Programme B & INPRO
Chaitanyamoy GANGULYHead , Nuclear Fuel Cycle & Materials Section
Division of Nuclear Fuel Cycle & Waste TechnologyDepartment of Nuclear Energy
International Atomic Energy Agency

NUCLEAR FUEL CYCLENUCLEAR FUEL CYCLE
Natural Uranium & Thorium
For nuclear energy to be sustainable as a global source of emission free energy, the reactor fuel cycle must also remain sustainable (DG-IAEA Scientific Forum 2004)
Natural Uranium & Natural Thorium are the basic raw materials for nuclear fuels.

General Features of Uranium and Thorium Fuel CycleGeneral Features of Uranium and Thorium Fuel Cycle
Pu 239 : best fissile material forU238-Pu239 cycle in fast reactor
U233: best fissile material forTh232-U233 cycle in thermal reactor

IAEA Major Programme 1.2 (Prog. B) Nuclear Fuel Cycle & Materials Technology
To facilitate development of nuclear fuels and fuel cycle technologies that:i) are economically viable;ii) make efficient use of uranium and thorium natural resources; iii) are safe; iv) generate minimum quantities of high level wastes; v) are proliferation-resistant; vi) are sustainable.
Subprog. 1.2.1 (B1) Uranium Resources & Production and Databases for Nuclear Fuel Cycle Working Group for B1: OECDNEA IAEA Uranium Group(~34 members including EU), Databases iNFCIS [NFCSS, UDEPO, NFCIS, PIE, MADB]
Subprog. 1.2.2 (B2) Nuclear Power Reactor Fuel Engineering Working Group for B2: Technical Working Group on Nuclear Fuel Performance and Technology (TWGFPT)(28 Members including OECD/NEA & EC)
Subprog. 1.2.3 (B3) Management of Spent Fuel from Nuclear Power ReactorsSubprog. 1.2.4 (B4) Topical Issues of Nuclear Fuels and Fuel Cycle for Advanced and Innovative Reactors
Working Groups for B3&B4: Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWGNFCO) (~41 members including ISTC, OECD/NEA & EC)
International Working Group

Identified Resources (8 000>2 500Fast reactors with closed fuel cycle and recycling.
> 675300100Current technology
Using Total Conventional and Unconventional
Phosphate Resources
Using Total Conventional
Resources
Using only Identified Resources
Reactor/Fuel cycle

Canada 8%
USA6%
Brazil6%
Niger5%
Namibia5%
Australia22%
South Africa8%
Russian Fed.10%
Kazakhstan15%
Uzbekistan2%
China1%
Ukraine4%
India1%
Distribution of Identified Uranium resources Worldwide Distribution of Identified Uranium resources Worldwide (Is the supply secure?) (Is the supply secure?)
Total Identified Resources: 5.55 Mt (2007) Total Identified Resources: 5.55 Mt (2007)

Important data on Uranium resources, production, front-end of Uranium Fuel Cycle and Nuclear Power worldwide
(as on Nov. 2008)Uranium Production
(Mines & Mills) UF6
Conversion Enrichment Uranium
Fuel Fabrication
Reactors in Operation Reprocessing
MOX Fabrication
Identified Reserves
(

REVIVAL OF IAEAs URANIUM PRODUCTION APPRAISAL TEAM (UPSAT) in 2008[UPSAT Guidelines : Ref: IAEA-TECDOC-878(1996)]
The IAEA Uranium Production Site Appraisal Team (UPSAT) programme is designed to assist Member States to improve the Operational and Safety performance of Uranium Production Facilities by peer review by a team of selected International Experts having direct experience in the technical areas specific to that operation.Member States should make a formal request to
IAEA for UPSAT service.
The major areas to be considered in developing the programme for an UPSAT mission areOrganization and management;Mining Ore milling and processing engineering;Staff training;Waste management;General safety and Radiation protection;Monitoring systems;Environmental impact assessment;Security;Decommissioning/environmental remediation planning

TYPICAL FUELS FOR OPERATING NUCLEAR POWER REACTORS IN THE WORLDTYPICAL FUELS FOR OPERATING NUCLEAR POWER REACTORS IN THE WORLD
ZrZr--1%Nb clad1%Nb clad(

FUEL FORMSFUEL FORMS
Pebble Bedcoated particle fuels embedded in spherical shapeGermany, South Africa, China
Pebble fuel elementPebble has diameter of 60 mm
TRISO Coated fuel particles (left) are formed into fuel rods (center) and inserted into graphite fuel elements (right)
COATED RTICLES COMPACTS FUEL ELEMENTS
Pyrolytic CarbonSilicon CarbidePorous Carbon BufferUCO Kernel
Prismatic block
US, Japan, Russia and France
Trisocoated particle
B: Coated Fuel Particles1. Coated fuel particles for HTGR
2. Fuel particles (dry or wet route) for vibratory compacted fuel pins

Coordinated Research Projects: Fuel element performance modelling
(Fuel Modelling at Extended Burnup, FUMEX-II 2002-2007, FUMEX-III started in Dec.2008, RCM, Vienna)
Optimisation of water chemistry(Optimisation of coolant water chemistry to ensure reliable fuel performance at high burnup and in ageing plants FUWAC 2007-2010)
Delayed hydride cracking of Zr alloys(DHC-II, fuel cladding materials, 2005-2009)
Simulation & Modelling of Radiation Effects(SMoRE) started in November 2008(RCM, Vienna)
Natural
IAEA Technical Working Group on Fuel Performance & Technology (TWGFPT)
Data Bases: IAEA PIE Data Base Joint IAEA-OECD/NEA IFPE Data BaseExpert Reviews: Handbook on Zirconium & its Alloys for Nuclear Applications (final draft in 2008) Fuel Failures Review (final draft in 2008)
Subprogramme 1.B.2Nuclear Power Reactor Fuel Engineering
(focus on LWRs and PHWRs)

NFCIS NFCIS (Nuclear Fuel Cycle Information System) Directory of Civilian Nuclear Fuel
Cycle Facilities Worldwide Facilities from uranium milling to
reprocessing, spent fuel storage and heavy water production
Includes facilities at planning stage and decommissioned
Available online since 2001
NFCSSNFCSS(Nuclear Fuel Cycle Simulation System) Scenario based simulation system Estimates nuclear fuel cycle
material and service requirements Calculates spent fuel arisings and
actinide contents The simple web version is
expected to be online as of end of 2005
UDEPO UDEPO (World Distribution of Uranium Deposits) Technical and geological
information on uranium deposits Country level maps of the deposits
will be displayed on the web site Deposits containing 0.03%U3O8
included More than 800 deposits stored in
the database Available online since 2004
MADB MADB (Minor Actinide Property Database) Bibliographical database on
physico-chemical properties of minor actinides bearing materials
Carbides, Nitrides, Alloys, Oxides, Halides, Elements and other forms are covered
More than 750 data records from 164 publications
Under development
PIEPIE(Post Irradiation Examination) Catalogue of PIE facilities
worldwide General information about the
facilities Technical capabilities of the
facilities Available online since 2004
www-nfcis.iaea.org

Input and output information flow in Nuclear Fuel Cycle Simulation System(NFCSS) code
Input Output
NFCSS
Strategy Parameters Nuclear power projections Reprocessing-recycling
strategies Reactor mixtures Load factors
Fuel Parameters Avg. discharge burnup Avg. initial enrichment Avg. tails assay
Control Parameters Share of MOX fuel in core Lead and lag times for
different processes # of reprocessing cycles
Natural uranium requirements
Conversion requirements
Enrichment requirements
Fresh fuel requirements
Spent fuel arisings
Plutonium accumulation
Minor Actinide accumulation
Reprocessing requirements
MOX fuel fabrication requirements
CAINCalculation of Actinide
Inventory
Input Output
NFCSS
Strategy Parameters Nuclear power projections Reprocessing-recycling
strategies Reactor mixtures Load factors
Fuel Parameters Avg. discharge burnup Avg. initial enr

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