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WNU - Ottawa 1Jacques BOUCHARD, July 15, 2008
Next Generation Nuclear Reactors
Jacques BOUCHARDCommissariat à l’Energie Atomique
FRANCE
WNU - Ottawa 2Jacques BOUCHARD, July 15, 2008
Session Contents
- Introduction- Nuclear Reactor Generations ; A brief history- Light Water Reactors- High Temperature Reactors- Fast Neutron Reactors- The Generation IV International Forum (GIF)- The IAEA program (INPRO)- Other initiatives- Discussion
WNU - Ottawa 3Jacques BOUCHARD, July 15, 2008
Introduction
- Nuclear Energy
- Safety principles
- Economy
- Public acceptance
WNU - Ottawa 4Jacques BOUCHARD, July 15, 2008
Introduction : Nuclear Energy
- A high density of energy- A process controlled through delayed neutrons- Radioactivity of fission products- Fissile and fertile isotopes- Criticality criteria- The front end of the fuel cycle- The back end of the fuel cycle
Mastering the energy from the fission of heavy nuclides
WNU - Ottawa 5Jacques BOUCHARD, July 15, 2008
Introduction : Safety Principles
- Two main risks:- Uncontrolled increase of power- Loss of cooling
- Inherent safety features
- Protection and actions
- Mitigation of severe accidents
- Other types of risks
WNU - Ottawa 6Jacques BOUCHARD, July 15, 2008
Introduction : Economy – capital cost
Nuclear energy :•• High capital investment costsHigh capital investment costs• Long planning horizons• Low Fuel and O&M costs
%
WNU - Ottawa 7Jacques BOUCHARD, July 15, 2008
Introduction : Public Acceptance
- Several issues:- Civilian vs. military applications- plant safety, in particular severe accidents,- waste management
- Strong improvements in communication and transparency
- New positive aspects (economy, climate change…)
- A real need for education
WNU - Ottawa 8Jacques BOUCHARD, July 15, 2008
Nuclear Reactor Generations
Generation I
Generation II
1950 1970 1990 2010 2030 2050 2070 2090
Generation III
First First ReactorsReactors
Current Current ReactorsReactors
Advanced Advanced ReactorsReactors
Future Future SystemsSystems
Generation IV
WNU - Ottawa 9Jacques BOUCHARD, July 15, 2008
Generation I : Early Prototypes
- Many prototypes all around the world
- Various types of thermal and fast neutron reactors
- For most of the countries, a main limitation due to the use of natural uranium
-> graphite or heavy water moderated cores
- Development of the first light water reactors for naval propulsion
- First production of electricity in ARCO (Idaho) 1951, with a fast neutron reactor
Reactors built in the fifties and sixties
WNU - Ottawa 10Jacques BOUCHARD, July 15, 2008
Generation II : Current Power Plants
- An industrial development accelerated by the first oil shocks
- A large domination of light water reactors :- Pressurized Water Reactors- Boiling Water Reactors
- Some countries made other choices:- Heavy Water Reactors (CANDU)- Gas Cooled Reactors (AGR)- Light Water Cooled Graphite Reactors (RBMK)
- An expansion stopped in many countries after the TMI and Chernobyl accidents
Reactors built from the end of the sixties to the nineties
WNU - Ottawa 11Jacques BOUCHARD, July 15, 2008
Generation II : Current Power Plants
Status of existing power reactors (2005): The families
Type Nb of units Total Capacity(GWe)
PWR 267 241
BWR 93 83
PHWR 41 21
GCR 22 11
LWGR 16 11
FBR 2 1
Total 441 368
WNU - Ottawa 12Jacques BOUCHARD, July 15, 2008
Generation II : Current Power PlantsStatus of existing power reactors connected to the grid (2005): The countries
Country Nb of units Capacity (GWe)
United States 103 98France 59 63Japan 55 48Russia 31 22
United Kingdom 23 12South Korea 20 17
Ukraine 15 13Others (22) 100 63
Germany 17 20Canada 18 12
Total 441 368
WNU - Ottawa 13Jacques BOUCHARD, July 15, 2008
Generation III : Advanced Reactors
- A new generation of reactors which design takes benefit of the large experience acquired in the operation of Gen II plants and of the lessons coming from TMI
- Light Water Reactors are still dominating
- To make new improvements in safety while keeping economic competitiveness have been the main objective
- Different approaches have been studied and are still competing in the industrial offer :
- small vs. large reactors- passive vs. active safety systems
- Mitigation of severe accident consequences is a major step
Near term deployment of industrial reactors
WNU - Ottawa 14Jacques BOUCHARD, July 15, 2008
Generation III : The industrial offer
Generation III reactors identified as‘Near Term Deployment’ by the Generation IV Forum
Advanced Pressurized Water Reactors
AP 600, AP 1000, APR1400, APWR+, EPR
Advanced Boiling Water ReactorsABWR II, ESBWR, HC-BWR, SWR-1000
Advanced Heavy Water Reactors
ACR-700 (Advanced CANDU Reactor 700)
Small and middle range power integrated Reactors
CAREM, IMR, IRIS, SMART
High Temperature, Gas Cooled, Modular ReactorsGT-MHR, PBMR
WNU - Ottawa 15Jacques BOUCHARD, July 15, 2008
Generation III : Market prospective
Country Nb Reactors Mean Age
United States 103 30 years
France 59 20 years
Japan 55 19 years
United Kingdom 23 31 years
Sweden 10 25 years
Germany 17 23 years
Belgium 7 28 years
China 9 6 years
Finland 4 25 years
Average values of current NP age (2005)
WNU - Ottawa 16Jacques BOUCHARD, July 15, 2008
Generation III : Market prospective
- Besides the renewal of existing power plants, there are many plans for new realizations (USA, China, India, UK…);
- The nuclear production capacity could grow from 400 GWe to 1000 - 1500 GWe by 2050.
- Most of the new nuclear plants in the three or four coming decades will be Gen III systems.
WNU - Ottawa 17Jacques BOUCHARD, July 15, 2008
Generation IV : Future Nuclear Systems
- Prospects for energy needs show the possibility of a strongly increasing demand for nuclear power;
- In such an hypothesis, sustainability becomes a predominant concern, which means preservation of natural resources, waste minimization and proliferation resistance are criteria as important as economy and safety.
- Furthermore, other application of nuclear energy than electricity production are to be considered, in particular, hydrogen production, industrial use of heat or desalination.
- The development of new systems will take time and require validation and demonstration. Therefore, the target for industrial scale applications is 2030 or later.
R&D in preparation for a large expansion of nuclear energy
WNU - Ottawa 18Jacques BOUCHARD, July 15, 2008
•• Concepts with breakthroughsConcepts with breakthroughsMinimization of wastesPreservation of resourcesNon Proliferation
•• Gradual improvements in :Gradual improvements in :CompetitivenessSafety and reliability
Systems expected to reach technical maturity by 2030Systems expected to reach technical maturity by 2030
Assets for new marketsAssets for new markets- hydrogen production- direct use of heat- sea water desalination
An internationally shared R&DAn internationally shared R&D
New requirements for sustainable nuclear energyNew requirements for sustainable nuclear energy
Generation IV : An International Forum (GIF)
WNU - Ottawa 19Jacques BOUCHARD, July 15, 2008
Light Water Reactors
- One technology but two different designs:- boiling water reactors- pressurized water reactors
- More than 10 000 equivalent year. reactor experience- 350 large power reactors in operation in 25 countries- Only one severe accident (TMI) with limited consequences- Initial lifetime expected to be expanded by many years- Considerable economic improvement through more than twenty years of operation- Strong evolution of the design from Gen II to Gen III- Two main limitations:
- temperature below 300°C which means rather low yields- neutron balance which leads to poor regeneration rates
A mature technology with the largest experience
WNU - Ottawa 20Jacques BOUCHARD, July 15, 2008
LWR : Continuous improvements
• Increasing capacity factors(equivalent to 23 new reactors)
• Excellent safety performances• Reduction of O&M costs• Reduction of wastes quantities• Reduction of exposure at work
767 778754
728
674640
577
500
600
700
800
'90 '94 '98 '99 '00 '01 '02
(Bill
ions
of K
ilow
att-H
ours
)
91%90,7%
0,0%
20,0%
40,0%
60,0%
80,0%
100,0%
'92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02
Ca
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ac
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0,04 0,03 0,02 0,030
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88 89 90 91 92 93 94 95 96 97 98 99 2000 2001
Fiscal Year
Sign
ifica
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vent
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(Source ANS)
Cap
acity
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Sign
ifica
ntev
ents
(Bill
ions
of K
Wh)
The US example
WNU - Ottawa 21Jacques BOUCHARD, July 15, 2008
LWR : a competitive energy
Source: EDF
Europe : Comparison of markets prices between fuel (coal, fuel oil, natural gas, nuclear) and power
0
10
20
30
40
50
60
janv-00
avr-00
juil-00
oct-00
janv-01
avr-01
juil-01
oct-01
Eur
os/M
Wh
Power Gas Coal Fuel Nuclear
Comparison of European power market prices and operating costs for different type of fuels
oil
WNU - Ottawa 22Jacques BOUCHARD, July 15, 2008
Light Water Reactors : Generation III
- Lessons drawn from the TMI accident
- A further reduction of severe accident probability
- Mitigation of consequences in case of core melting
- Passive vs. active systems
- A long story of R & D and engineering works
New improvements for safety
WNU - Ottawa 23Jacques BOUCHARD, July 15, 2008
Light Water Reactors : Generation III
Westinghouse : AP1000
WNU - Ottawa 24Jacques BOUCHARD, July 15, 2008
Light Water Reactors : Generation III
WNU - Ottawa 25Jacques BOUCHARD, July 15, 2008
Light Water Reactors : Generation III
AREVA – NP’s EPR
Le Le projetprojet EPREPR
Core meltspreading area
Double-wall containmentwith ventilation and filtration system
Containmentheat removalsystem
Four-trainredundancyfor main safeguardsystems
Inner refuelingwater storage tank
Inner refuelingwater storage tank
EPR
Improved safety
WNU - Ottawa 26Jacques BOUCHARD, July 15, 2008
Corium spreading test : CEA - VULCANOMelt spreading phenomena have been extensively investigated
real UO2 with some ZrO2
WNU - Ottawa 27Jacques BOUCHARD, July 15, 2008
LWR Gen III : Back end of the fuel cycle
Plutonium annual balanceKg Pu/year
REP 900 UO2 : + 200
REP 900 MOX : 0
EPR 100% MOX : - 670
Capacity to load up to 100% MOX Core
MOX
UOXControl rods
EPRREP 900
An enhanced capacity to burnPlutonium
WNU - Ottawa 28Jacques BOUCHARD, July 15, 2008
LWR : A challenge for other technologies
- From the beginning, scientists and engineers are looking to other technologies in a try to overcome the two main LWR limitations:
- Thermodynamic yield limited by rather low temperatures,- Uranium burning limited by small breeding rates.
- Two main paths have been and are still considered, high temperature reactors and fast neutron reactors.
- Other technologies can bring some improvements in one or the other way, such as supercritical water systems or molten salt reactors, but have not yet reached the same level of development.
WNU - Ottawa 29Jacques BOUCHARD, July 15, 2008
High Temperature Reactors
- Direct use of heat for industrial applications, including possible hydrogen productions by chemical processes, requires temperatures in the range 800 – 1000 °C.- Gas cooling is the only solution and among gases helium is the most practical choice.- A first try to develop that technology took place in the 70s (Fort St Vrain in the US, THTR in Germany) after some early prototypes.- Small experimental reactors have been built more recently in Asia (HTTR in Japan, HTR 10 in China).- New projects are considered in the frame of Gen III (PBMR in South Africa) or Gen IV ( NGNP in the US).
A new path for both electricity and hydrogen productions
WNU - Ottawa 30Jacques BOUCHARD, July 15, 2008
High Temperature Reactors
Source: General Atomics
WNU - Ottawa 31Jacques BOUCHARD, July 15, 2008
High Temperature Reactors : The challenges
1 – The fuel : Small particles with carbon and SiC coatings; particles embedded in graphite; two options:
- compacts (FSV, GT-MHR)- pebbles (THTR, PBMR)
2 – Structural materials : Graphite is the basic material inside the core;
3 – The cooling system : helium loops with direct conversion (Brayton cycle) or indirect conversion through heat exchangers.
4 – Reactor power : limited by low power density and high gas pressure; still more limited in the pebble option by the controlof core reactivity.
WNU - Ottawa 32Jacques BOUCHARD, July 15, 2008
High Temperature Reactors : The fuel
Prismatic fuel element with TRISO particles(source: General Atomics)
WNU - Ottawa 33Jacques BOUCHARD, July 15, 2008
High Temperature Reactors
HTTR (Japan)
WNU - Ottawa 34Jacques BOUCHARD, July 15, 2008
High Temperature Reactors
HTR 10 (China)
WNU - Ottawa 35Jacques BOUCHARD, July 15, 2008
Main Power SystemReactor Unit
Recuperators
Compressors
Turbine
Generator
Contaminated Oil Lube System
Un-contaminated Oil Lube System
Shut-off DiskCBCS & Buffer Circuit
CCS & Buffer Circuit
Inter-cooler
Pre-cooler
Reactor Unit
Recuperators
Compressors
Turbine
Generator
Contaminated Oil Lube System
Un-contaminated Oil Lube System
Shut-off DiskCBCS & Buffer Circuit
CCS & Buffer Circuit
Inter-cooler
Pre-cooler
High Temperature Reactors
PBMR (South Africa)
WNU - Ottawa 36Jacques BOUCHARD, July 15, 2008
• Thermal spectrum, once-through uranium cycle
• Prismatic block or pebble bed fuelsHighly ranked in economics & in safety and reliabilityHydrogen production & other process-heat applications
VHTR Very High Temperature Reactor
WNU - Ottawa 37Jacques BOUCHARD, July 15, 2008
Iodine-Sulfur process for hydrogen production
Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen
H2O22
1
900 C400 C
Rejected Heat 100 C
Rejected Heat 100 C
S (Sulfur)Circulation
SO2+H2O+O22
1H2SO4
SO2+
H2OH2O
H2
I2+ 2HI
H2SO4
SO2+H2OH2O
+
+ +
I (Iodine)Circulation
2H I
I2
I2
WaterWater
Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen
H2O22
1 O22121
900 C400 C
Rejected Heat 100 C
Rejected Heat 100 C
S (Sulfur)Circulation
SO2+H2O+O22
1H2SO4
SO2+
H2OH2O
H2
I2+ 2HI
H2SO4
SO2+H2OH2O
+
+ +
I (Iodine)Circulation
2H I
I2
I2
WaterWater
WNU - Ottawa 38Jacques BOUCHARD, July 15, 2008
Fast Neutron Reactors
- Fast neutrons allow a more efficient burning of actinides because the ratio of fission/capture cross sections is higher than with thermal neutrons.
- The first consequence is the possibility of positive breeding gains which allows to burn all the uranium through conversion of Uranium 238 in Plutonium 239.
- Another interesting feature is the possibility of burning all the actinides produced in the fast reactors themselves or in light water reactors by continuous recycling, thereby reducing considerably the long term radioactive potential of waste.
A solution for both an optimized use of resources and waste minimization
WNU - Ottawa 39Jacques BOUCHARD, July 15, 2008
0
10
20
30
40
50
60
2000 2020 2040 2060 2080 2100
Years
Mt
Uranium Needs
Estimated resources
Speculative resources
Phosphate
Sea water,others
< 13
0 $/
kg
< 20
0 $/
kg Betw
een
200
up to
400
$/kg
Hig
her t
han
1000
$/k
g
Scenario PWR only open cycle (IAASA A2)
Engaged UConsumed U
WNU - Ottawa 40Jacques BOUCHARD, July 15, 2008
Recycling to optimize the use of uranium resources
1000 kg U nat
100 kg U 5%
900 kg U dep
Recycling
4 kg W + PF
1 kg Pu
95 kg U rep
Fast neutron reactors burn plutonium while converting U 238 intoplutonium that is burnt in situ (regeneration breeding of fissile fuel)
The existing depleted uranium that is stored today in France is worth 5000 years of current nuclear production.
Enrichment
WNU - Ottawa 41Jacques BOUCHARD, July 15, 2008
• Growing energy demand ;• Part of nuclear energy increasing after 2030;• Light Water Reactors with uranium fuel remain dominant.
A plausible scenario
2005 2025 2050
World Energy needs (GTOE) 10 15 20
Nuclear primary energy (GTOE) 0.7 1.2 2.5
Nuclear capacity (GWe) 360 650 1400
LWR capacity (GWe) 320 550 1200
WNU - Ottawa 42Jacques BOUCHARD, July 15, 2008
• ‘The plausible scenario’;• R&R limited to a few countries;• Gen IV systems implemented progressively after 2040.
Spent Fuel and Plutonium Accumulation
2005 2025 2050
LWR capacity (GWe) 320 550 1200
Stored spent fuels ( Mtons) 0,2 0,5 1,0
Nuclear capacity (GWe) 360 650 1400
Plutonium amount (tons) 1500 4000 8500
WNU - Ottawa 43Jacques BOUCHARD, July 15, 2008
Fast Reactors : Resources optimization
0
10
20
30
40
50
2000 2020 2040 2060 2080 2100Year
Cum
ulat
ive
Nat
ural
U(M
illio
n To
nnes
)
LWR Once Through
FR Introduced 2050
FR Introduced 2030
Known Resources
Speculative Resources
0
10
20
30
40
50
2000 2020 2040 2060 2080 2100Year
Cum
ulat
ive
Nat
ural
U(M
illio
n To
nnes
)
LWR Once Through
FR Introduced 2050
FR Introduced 2030
Known Resources
Speculative Resources
Cu
mula
tive N
atu
ral
U(M
illio
n T
on
ne
s)
LWR Once Through
WNU - Ottawa 44Jacques BOUCHARD, July 15, 2008
Fast Reactors : Waste minimization
Plutonium recycling
Spent FuelDirect disposal
Uranium Ore (mine)
Time (years)
Rel
ativ
e ra
dio
toxi
city
P&T of MA
Pu +MA +FP
MA +FP
FP
WNU - Ottawa 45Jacques BOUCHARD, July 15, 2008
Global Actinide Recycling
• Saving uranium resources
• Minimizing waste heat and radiotoxicity
• Ensuring a strong proliferation resistance
Unat
Actinides
Spentfuel
Ultimatewastes
FP
GEN IV FR
Treatment and
Re-fabrication
WNU - Ottawa 46Jacques BOUCHARD, July 15, 2008
Global Actinide Recycling
No separation of pure elements, in particular Plutonium
Very low quantities of actinides in the ultimate waste
An efficient burning (by fission) of actinides in the reactor, in order to avoid growing inventories of heavy elements
The requirements
WNU - Ottawa 47Jacques BOUCHARD, July 15, 2008
Fast Neutron Reactors : Technologies
- To keep a fast neutron system it is necessary to avoid light elements in the core and in particular for the cooling system.- The two main possibilities for cooling are liquid metals or gases. They are part of Gen IV selected systems.- A broad worldwide effort have been devoted to sodium cooling technology including industrial prototypes (BN600 in Russia, Superphenix in France, Monju in Japan).- The Russians have used lead cooling for naval reactors and some more studies have been made for possible use of lead or lead-bismuth cooling systems.- The use of helium technology developed for HTGRs is also considered for fast reactors.- After a negative attempt to use vapor cooling, supercritical water has been selected by the GIF as a possible candidate for fast reactor cooling.
WNU - Ottawa 48Jacques BOUCHARD, July 15, 2008
Fast Reactors : Sodium Technology
- Sodium is a very suitable coolant:- liquid in a wide range of temperatures (90 – 890°C)- mono isotope (Na23)- thermodynamics parameters- no corrosion (when purified)
- Large industrial experience :- various industrial uses- 40 years of technological studies for nuclear applications- many prototypes
- Well-known drawbacks :- chemical reactivity (sodium fires and sodium-water reactions)- difficulties for handling and inspection
WNU - Ottawa 49Jacques BOUCHARD, July 15, 2008
SFR Sodium-Cooled Fast Reactor
The pool design
WNU - Ottawa 50Jacques BOUCHARD, July 15, 2008
Phenix
WNU - Ottawa 51Jacques BOUCHARD, July 15, 2008
ElectricalPower
GeneratorTurbine
Condenser
Heat Sink
Pump
Pump
Pump
PrimarySodium?Cold?Cold Plenum
Hot Plenum
PrimarySodium?Hot?
Control Rods
Heat?Exchanger
Steam Generator
Core
SecondarySodium
ElectricalPower
GeneratorTurbine
Condenser
Heat Sink
Pump
Pump
Pump
PrimarySodium
ColdCold Plenum
Hot Plenum
PrimarySodium
Hot
Control Rods
Heat Exchanger
Steam Generator
Core
SecondarySodium
SFR Sodium-Cooled Fast Reactor
The loop design
WNU - Ottawa 52Jacques BOUCHARD, July 15, 2008
� � �� � �D/ G
Reactor bldg.
Secondary pump
Air cooler
Fuel
Coolers
condenser
OutletHeat
exchangers
FBR Prototype Monju (Japan)
4
DG Bat.
WNU - Ottawa 53Jacques BOUCHARD, July 15, 2008
BN 600 (Russia)A 600 MWe plant built at Beloyarsky (Russia)First criticality: 1980; still in operation
WNU - Ottawa 54Jacques BOUCHARD, July 15, 2008
SUPERPHENIXA 1200 MWe plant built at Creys-Malville (France)First criticality: 1985; Shutdown: 1997
WNU - Ottawa 55Jacques BOUCHARD, July 15, 2008
Fast Reactors : Lead Technology
- A candidate to avoid the risks associated with sodium fires or sodium-water reactions
- A less favorable coolant (thermodynamics parameters, corrosion risks)
- lead-bismuth alloy to reduce corrosion risks
- An experience limited to Russian applications in naval propulsion
- Many studies going on in various countries
WNU - Ottawa 56Jacques BOUCHARD, July 15, 2008
LFR Lead-cooled Fast Reactor
WNU - Ottawa 57Jacques BOUCHARD, July 15, 2008
Fast Reactors : Helium Technology
- Gas cooling is less efficient than liquid metal cooling
- The development of a gas cooled fast reactor will require a new type of fuel
- Helium technology is already considered for VHTR
- Specific safety concerns which should be clarified
- If it can be successfully designed, the result will satisfy both objectives for a sustainable development (fast neutron physics and high temperature technology)
WNU - Ottawa 58Jacques BOUCHARD, July 15, 2008
GFR Gas-Cooled Fast Reactor
WNU - Ottawa 59Jacques BOUCHARD, July 15, 2008
Generation IV International Forum
WNU - Ottawa 60Jacques BOUCHARD, July 15, 2008
The Gen IV Structure
WNU - Ottawa 61Jacques BOUCHARD, July 15, 2008
Very High Temperature Reactor
Six innovative concepts with technological breakthroughs
Sodium Fast reactor
Closed Fuel Cycle
Once Through
Supercritical Water Reactor
Once/Closed
Molten Salt Reactor
Closed Fuel Cycle
Closed Fuel Cycle
Lead Fast Reactor
Gas Fast Reactor
Closed Fuel Cycle
WNU - Ottawa 62Jacques BOUCHARD, July 15, 2008
GIF Collaborative R&D Structure
MSR SALFR SA
Framework Agreement
AdvancedFuel PA
Component Design &
Balance of Plant PA
System Integration & Assessment
PA
Fuel, Core Materials &
Fuel Cycle PA
Fuel & Fuel Cycle PA
H2 Production PA
SFR SA VHTR SA
GACID PA
System Integration
& Assessment
PA
GFR SA
Legend :PA :Project ArrangementSA: System Arrangement,
Signed
Not yet signed
Materials PA
SCWR SA
Material & Chemistry PA
Thermal-Hydraulic & Safety PA
System Integration & Assessment
PA
WNU - Ottawa 63Jacques BOUCHARD, July 15, 2008
Signature of the Generation IV Framework Agreement on 28th February 2005 in Washington DC
WNU - Ottawa 64Jacques BOUCHARD, July 15, 2008
Charter Signing Ceremony by China and Russia – Paris, 11/06
WNU - Ottawa 65Jacques BOUCHARD, July 15, 2008
VHTR SA Signing Ceremony – Paris, 11/06
WNU - Ottawa 66Jacques BOUCHARD, July 15, 2008
The IAEA INPRO
• INPRO : International Project on InnovativeNuclear Reactors and Fuel Cycles.
• Basis of INPRO : Resolution at the IAEA GeneralConference in 2000 in Vienna and at the United Nations General Assembly in 2001.
● Text of IAEA General Conference Resolution in September 2000:
o IAEA GC 2000 has invited “all interested Member States to combine their efforts under the aegis of the Agency in considering the issues of the nuclear fuel cycle, in particular by examininginnovative and proliferation-resistant nuclear technology”
WNU - Ottawa 67Jacques BOUCHARD, July 15, 2008
General Objectives of INPRO
● INPRO General Objectives:1. To help to ensure that nuclear energy is available to
contribute in fulfilling energy needs in the 21st century in a sustainable manner.
2. To bring together both technology holders and technology users to consider jointly the actions required to achieve desired innovations in nuclear reactors and fuel cycles.
• INPRO Time horizon is 50 years into the future.
WNU - Ottawa 68Jacques BOUCHARD, July 15, 2008
GIF and INPRO Membership
(as of May 2006)
GIF has an R&D Framework with most of the countries with large
R&D programs or industries
INPRO has participation of most of the countries with nuclear reactors or
plans to acquire them
WNU - Ottawa 69Jacques BOUCHARD, July 15, 2008
Current Scope of Activities
WNU - Ottawa 70Jacques BOUCHARD, July 15, 2008
The US initiative GNEP
• Growing Nuclear Energy Demand
• Advanced Fuel Cycle
• Fast Reactors burning Actinides
• Small Reactors for countries starting with nuclear
• International Partnership– Advanced fuel cycle technology– Fuel services for countries without fuel cycle facilities
WNU - Ottawa 71Jacques BOUCHARD, July 15, 2008
Future Prototypes : VHTR
NGNP ( USA, Idaho)
WNU - Ottawa 72Jacques BOUCHARD, July 15, 2008
Future Prototypes : Fast Reactors
January 2006Presidential Announcement:Construction of a 4th
generation reactor prototype in 2020
February 2006�Global Nuclear EnergyPartnership (GNEP)GNEP Fast Reactor in 2020-2025
Generation IV International Forum (GIF)
April 2006:Fast Reactor Cycle Technology Development
(FaCT) projectDemo / Fast reactor in 2025