generation iv concepts and international frames

Demanova, Slovakia, Feb 2010GEN IV concepts & International frames 1

Generation IV Concepts and International Frames

Pascal ANZIEUCEA, [email protected]


Generation IV

Generations of Nuclear Power Systems

Generation II

1950 1970 1990 2010 2030 2050 2070 2090

Generation III

GGPWR

PWR, BWR, CANDU EPR, AP1000 … Generation IV

SFR + Closed fuel cycle

OPERATIONOPTIMIZATION

Generation I DISMANTLING


New applicationsNew applicationsHydrogen, drinkable water, heat

Industrial deployment ~2040Industrial deployment ~2040

Multilateral cooperation with 3 Multilateral cooperation with 3 levels of agreements:levels of agreements:

New requirements to supporta sustainable development

Generation IV International Forum

Steady Progress:Steady Progress:- Economic competitiveness- Safety and reliability

Nuclear Power for centuriesNuclear Power for centuries- Resource saving- HL Radwaste minimisation- Non-prolifération

IntergovernmentalIntergovernmentalSystems Systems R&D ProjectsR&D Projects

E.U.

ChinaChina RussiaRussia

Charter:July 2001

Frameworkagreement:

February 2005


Key Steps to Prepare the RoadmapCharter signed in July 2001 to:• Identify potential areas of multilateral

collaborations on Generation IV nuclear energy systems

• Foster collaborative R&D projects• Establish guidelines for collaboration and

reporting of their results (review, recommendations, …)

• Define Technology Goals for Generation IV• Identify Concepts with Potential• Evaluate Concepts with a Common and

Consistently Applied Methodology• Identify R&D Gaps and Needs• Roadmap Issued in December 2002

http://nuclear.gov/geniv/Generation_IV_Roadmap_1-31-03.pdf

January, 2003


Scoring for potential, significant advances in• Economics• Safety & Reliability• Sustainability• Security and non proliferation

Offering various energy applications• Electricity generation• Hydrogen, clean water (desalination), Heat

Composite and robust set of conceptsInnovation, leverage effect of R&D needsTime sequencing and opportunities for development

GENIV Vs. INTD list

Rationale for the selection


Nearly 100 technical experts contributing to the R&D planning

NERAC

GEN IV Roadmap NERAC Subcommittee

(GRNS)

Technical Community

• Industry

•Universities

•National Laboratories

DOE-NE

Roadmap Integration Team (RIT)

Evaluation Methodology

Water-Cooled Reactors

Gas-Cooled

Liquid-Metal-Cooled

Non-Classical Concepts

Technical Working Groups:

Fuel

Cyc

le C

ross

cut

Fuel

s &

Mat

eria

ls

Ris

k &

Saf

ety

Econ

omic

s

Ener

gy P

rodu

cts

2001 Generation IV International Forum (GIF)

Argentina Brazil France

S. AfricaKorea Switzerland UK US

Canada Japan

Overall GEN IV Roadmap organization


First level Goals for innovative systemsSustainability–1Generation IV nuclear energy systems will provide sustainable energy generation that meets clean air objectives and promotes long-term availability of systems and effective fuel utilization for worldwide energy production.Sustainability–2 Generation IV nuclear energy systems will minimize and manage their nuclear waste and notably reduce the long term stewardship burden in the future, thereby improving protection for the public health and the environment.Economics–1 Generation IV nuclear energy systems will have a clear life-cycle cost advantage over other energy sources.Economics–2 Generation IV nuclear energy systems will have a level of financial risk comparable to other energy projects.Safety and Reliability–1Generation IV nuclear energy systems operations will excel in safety and reliability. Safety and Reliability–2Generation IV nuclear energy systems will have a very low likelihood and degree of reactor core damage.Safety and Reliability–3Generation IV nuclear energy systems will eliminate the need for offsite emergency response.Proliferation Resistance and Physical protectionGeneration IV nuclear energy systems will increase the assurance that they are a very unattractive and least desirable route for diversion or theft of weapons-usable materials and provide increased physical protection against acts of terrorism.


2 4 M e t r ic s

R o l lu p o f M e t r ic s , C r i te r ia , G o a ls a n d G o a l A r e a s

P r o l i f e r a t io nR e s is ta n c e a n d P h y s ic a l P r o te c t io n P R 1 -2 V u ln e ra b il ity o f in s ta lla t io n s • P a s s iv e s a fe ty fe a tu r e s

S R 1 O p e ra t io n a l S a fe ty a n d R e lia b il it y

E C 1 L ife C y c le C o s t

S a fe ty a n d R e l ia b i l i t y

S u s ta in a b i l i t y

E c o n o m ic s

S U 1 R e s o u rc e U t il iz a t io n

P R 1 P ro life ra t io n R e s is ta n c e a n d P h y s ic a l P ro te c t io n

S U 1 -1 F u e l U t il iz a t io n

E C 1 -1 O v e r n ig h t c o n s t r u c t io n c o s ts

S R 1 -1 R e lia b il it y

P R 1 -1 S u s c e p t ib il it y to d iv e r s io n o r u n d e c la re d p ro d u c t io n

• U s e o f fu e l r e s o u rc e s

• O v e rn ig h t c o n s t r u c t io n c o s ts

• F o rc e d o u ta g e ra te

• S e p a ra te d m a te r ia ls• S p e n t fu e l c h a ra c te r is t ic s

S R 2 -1 R o b u s t s a fe ty fe a tu re s • R e lia b le r e a c t iv it y c o n t r o l• R e lia b le d e c a y h e a t r e m o v a l

S R 1 -2 W o rk e r /p u b lic - r o u t in e e x p o s u re

• R o u t in e e x p o s u re s

S R 1 -3 W o rk e r /p u b lic - a c c id e n t e x p o s u re

• A c c id e n t e x p o s u re s

S R 3 -2 R o b u s t m it ig a t io n fe a tu re s • L o n g s y s te m t im e c o n s ta n ts• L o n g a n d e f fe c t iv e h o ld u p

S R 2 -2 W e ll- c h a ra c te r iz e d m o d e ls• D o m in a n t p h e n o m e n a –

lo w u n c e r ta in ty• L o n g fu e l th e rm a l r e s p o n s e t im e• In te g r a l e x p e r im e n ts s c a la b il it y

S R 3 -1 W e ll- c h a ra c te r iz e d s o u rc ete rm /e n e rg y

• S o u rc e te rm• M e c h a n is m s fo r e n e rg y r e le a s e

S R 2 C o re D a m a g e

S R 3 O ffs ite E m e rg e n c y R e s p o n s e

S U 2 W a s te M in im iz a t io n a n d M a n a g e m e n t

S U 2 -1 W a s te m in im iz a t io n• W a s te m a s s• V o lu m e• H e a t lo a d• R a d io to x ic it y

S U 2 -2 E n v ir o n m e n ta l im p a c t • E n v ir o n m e n ta l im p a c t

E C 2 R is k to C a p ita lE C 2 -1 C o n s t ru c t io n d u ra t io n • C o n s t ru c t io n d u ra t io n

E C 1 -1 O v e r n ig h t c o n s t r u c t io n c o s ts • O v e rn ig h t c o n s t r u c t io n c o s ts

E C 1 -2 P ro d u c t io n c o s ts • P ro d u c t io n c o s ts

o f w a s te m a n a g e m e n t a n d d is p o s a l

1 5 C r i t e r ia8 G o a ls4 G o a l A r e a s

E C 2 -1 C o n s t ru c t io n d u ra t io n • C o n s t ru c t io n d u ra t io n

2 4 M e t r ic s

R o l lu p o f M e t r ic s , C r i te r ia , G o a ls a n d G o a l A r e a s

P r o l i f e r a t io nR e s is ta n c e a n d P h y s ic a l P r o te c t io n P R 1 -2 V u ln e ra b il ity o f in s ta lla t io n s • P a s s iv e s a fe ty fe a tu r e s

S R 1 O p e ra t io n a l S a fe ty a n d R e lia b il it y

E C 1 L ife C y c le C o s t

S a fe ty a n d R e l ia b i l i t y

S u s ta in a b i l i t y

E c o n o m ic s

S U 1 R e s o u rc e U t il iz a t io n

P R 1 P ro life ra t io n R e s is ta n c e a n d P h y s ic a l P ro te c t io n

S U 1 -1 F u e l U t il iz a t io n

E C 1 -1 O v e r n ig h t c o n s t r u c t io n c o s ts

S R 1 -1 R e lia b il it y

P R 1 -1 S u s c e p t ib il it y to d iv e r s io n o r u n d e c la re d p ro d u c t io n

• U s e o f fu e l r e s o u rc e s

• O v e rn ig h t c o n s t r u c t io n c o s ts

• F o rc e d o u ta g e ra te

• S e p a ra te d m a te r ia ls• S p e n t fu e l c h a ra c te r is t ic s

S R 2 -1 R o b u s t s a fe ty fe a tu re s • R e lia b le r e a c t iv it y c o n t r o l• R e lia b le d e c a y h e a t r e m o v a l

S R 1 -2 W o rk e r /p u b lic - r o u t in e e x p o s u re

• R o u t in e e x p o s u re s

S R 1 -3 W o rk e r /p u b lic - a c c id e n t e x p o s u re

• A c c id e n t e x p o s u re s

S R 3 -2 R o b u s t m it ig a t io n fe a tu re s • L o n g s y s te m t im e c o n s ta n ts• L o n g a n d e f fe c t iv e h o ld u p

S R 2 -2 W e ll- c h a ra c te r iz e d m o d e ls• D o m in a n t p h e n o m e n a –

lo w u n c e r ta in ty• L o n g fu e l th e rm a l r e s p o n s e t im e• In te g r a l e x p e r im e n ts s c a la b il it y

S R 3 -1 W e ll- c h a ra c te r iz e d s o u rc ete rm /e n e rg y

• S o u rc e te rm• M e c h a n is m s fo r e n e rg y r e le a s e

S R 2 C o re D a m a g e

S R 3 O ffs ite E m e rg e n c y R e s p o n s e

S U 2 W a s te M in im iz a t io n a n d M a n a g e m e n t

S U 2 -1 W a s te m in im iz a t io n• W a s te m a s s• V o lu m e• H e a t lo a d• R a d io to x ic it y

S U 2 -2 E n v ir o n m e n ta l im p a c t • E n v ir o n m e n ta l im p a c t

E C 2 R is k to C a p ita lE C 2 -1 C o n s t ru c t io n d u ra t io n • C o n s t ru c t io n d u ra t io n

E C 1 -1 O v e r n ig h t c o n s t r u c t io n c o s ts • O v e rn ig h t c o n s t r u c t io n c o s ts

E C 1 -2 P ro d u c t io n c o s ts • P ro d u c t io n c o s ts

o f w a s te m a n a g e m e n t a n d d is p o s a l

1 5 C r i t e r ia8 G o a ls4 G o a l A r e a s

E C 2 -1 C o n s t ru c t io n d u ra t io n • C o n s t ru c t io n d u ra t io n

4 objectives, 15 criteria et 24 performance indicators


Detailed Criteria for Safety and Reliability Goals

Safety and Reliability – 1. Generation IV nuclear energy systems operations will excel in safety and reliability.

SR1-1 ReliabilitySR1-2 Public and worker safety – routine exposuresSR1-3 Worker safety – accidentsSafety and Reliability – 2. Generation IV nuclear energy systems will have a very

low likelihood and degree of reactor core damage.SR2-1 Robust engineered safety featuresSR2-2 System models have small and well-characterized uncertainty (physical models / well-

scaled experiments)SR2-3 Unique characteristicsSafety and Reliability - 3. Generation IV nuclear energy systems will eliminate

the need for offsite emergency response.SR3-1 Radioactive source/energy release magnitude and timing understood and bounded by

inherent featuresSR3-2 Confinement or containment provides robust mitigation of bounding source and

energy releasesSR3-3 No additional individual riskSR3-4 Societal risk comparable to competing technology


120 Generation IV concepts classified in 19 homogeneous families

Gen IV - Roadmap : Systems Identification• Water-cooled reactors

– W1 - IPSR– W2 - SBWR– W3 - CANDU NG– W4 - SCWR, thermal– W5 - SCWR, fast– W6 - HC-BWR

• Gas-cooled reactors– G1 - PBR– G2 - PMR– G3 - VHTR– G4 - HTGR closed cycle– G5 - GFR

• Liquid-metal cooled reactors– L1 - Na cooled, MOX, aqueous– L2 - Na cooled, metal fuel, pyrometallurgy– L4 - Pb/Bi cooled, small– L5 - Pb/Bi cooled, large– L6 - Pb/Bi battery

• Non-classical reactors– N1- MSR– N2 - VCR– N3- AHTR (molten salt cooled)


Evaluation: capacity to sustainable development

Sustainability - 75th PercentileJanuary 25, 2002 Draft Evaluations

0

1

2

3

4

5

6

N3 L3 W4 W3 W2 G1 G2 G3 W1 N2 N1 G4 W6 W5 L4 L2 L5 L1 G5 L6

Concepts

Scor

e

Water (blue) Gas (yellow)

Metal (red) Non classical (green)Gas (yellow)


Safety & Reliability - 75th PercentileJanuary 25, 2002 Draft Evaluations

0

1

2

3

4

5

6

N1 W5 L3 W4 N2 L4 W6 G5 L5 L6 W2 L1 W3 N3 L2 W1 G3 G2 G4 G1

Concepts

Scor

e



Evaluation : Safety and Reliability


Economics - 75th PercentileJanuary 25, 2002 Draft Evaluations

0

1

2

3

4

5

6

W6 L3 W2 L5 N1 N2 N3 L4 W1 G5 L6 L1 L2 G2 W4 W5 G4 W3 G1 G3

Concepts

Scor

e



Evaluation : Economics and Competitiveness


Global Evaluation for all the concepts

75th Percentile Composite ScoresJanuary 25, 2002 Draft Evaluations

0

1

2

3

4

5

6

L3 N3 W6 N1 W2 N2 W4 L4 W5 W3 L5 W1 G5 G2 L6 L1 G1 G3 L2 G4

Concepts

Com

posi

te s

core



SFR-MOX

SFR-Meta

lHTR-C

losed

cycleHTR-P

ebble

VHTR

Pb/Bi B

atter

y

HTR-Pris

m

GFR


GIF: selection of six nuclear systems

Sodium-cooled Fast Reactor

Lead-cooled Fast Reactor

Molten Salt Reactor

Gas-cooled Fast Reactor

Supercritical Water-cooled ReactorVery High Temperature Reactor

Major potential of fast neutron systems with closed fuel cycle for breeding (fissile regeneration) and waste minimization (minor actinides transmutation)


Uranium Consumption

0

5

10

15

20

25

30

35

2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100Années

Ura

nium

nat

urel

con

som

mé

(Mt)

0

5

10

15

20

25

30

35

2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100Années

Ura

nium

nat

urel

con

som

mé

(Mt)

Natural Uranium World Consumption

Total available Resources (OCDE, AIEA)

Conventional Resources

Year

Use

d U

nat(

Mt)

Source : OECD and IAEA studies


• TC = PF/CF is called breeding ratio. The breeding gain is G = TC-1Only FRs can reach significant breeding gain• One necessary condition for breeding is :

η > 2η number of neutrons produced for each one

absorbed

1 for a new fission, 1 to convert fertile into fissilelosses

• This condition is well obtained at high energy, mainly with 239Pu

BREEDING CONDITIONSMOTIVATION & PRINCIPLES

• A nuclear reactor consumes fissile matter (CF) • 3U or 5U or 9Pu

• And produces it by transmuting fertile matter (PF) :• 238U ⇨ 239U ⇨ 239Np ⇨ 239Pu • ou 232Th ⇨ 233Th ⇨ 233Pa ⇨ 233U

Variation of η as a function of neutron energy


• Fast neutron Reactors operate with a spectrum of neutron not slow down

• So they do not use any moderator

• Their first advantage is a capacity for breeding. This is this only reactor line that can use all the natural uranium– 238U is transformed in 239Pu by a neutron capture

• LWRs use 0,5% U from mining as fuel; FRs can use 50% U – Resources are multiplied by a factor of 100– Consumption is possible for 5 000 to 10 000 years– FRs give sustainability to nuclear energy

MOTIVATION & PRINCIPLES

FRs : MAIN CHARACTERISTICS


Minor Actinides TransmutationNeptunium, Americium, Curium

Neutron capture induces formation of heavy elementsα ratio = capture/fission non favorable in thermal spectrum

Isotope

φ : Réacteur à neutrons lents (Rep)

φ : Réacteurs à neutrons rapides (RNR)

σf σc α σf σc α 235U 38,8 8,7 0,22 1,98 0,57 0,29 238U 0,103 0,86 8,3 0,04 0,30 7,5

239Pu 102 58,7 0,58 1,86 0,56 0,3 240Pu 0,53 210,2 396,6 0,36 0,57 1,6 241Pu 102,2 40,9 0,40 2,49 0,47 0,19 242Pu 0,44 28,8 65,5 0,24 0,44 1,8 237Np 0,52 33 63 0,32 1,7 5,3 241Am 1,1 110 100 0,27 2,0 7,4 243Am 0,44 49 111 0,21 1,8 8,6 244Cm 1,0 16 16 0,42 0,6 1,4 245Cm 116 17 0,15 5,1 0,9 0,18

Low neutrons reactor (LWR)

Fast neutrons reactor (FR)


Phased development of Fast Nuclear Energy Systems

1990

∼ 2020

> 2040

Safety standards / CodificationNon-proliferation standards

+ Physical protection, Safeguards…Resource utilizationWaste formTechnology International / National

U + Pu

FP + MAU

U + Pu+ MA

FP onlyU

Nat. resource conservationWaste minimizationProliferation resistance


Different systems for different applications

2000 2005 2010 2015 2020 2025 2030 2035 2040 2045 2050 2055 2060 20652000 2005 2010 2015 2020 2025 2030 2035 2040 2045 2050 2055 2060 2065

Hydrogen

Electricity Generation

Waste Burndown

Fissile Creation

Near-Term

Systems

Gen IIGen III

Gen IV


Nuclear Hydrogen for Transportation fuels & Industrial Processes

Electrolysis Thermo-chemical Cycle

TransportationDistribution

Storage

Primary Energy

Industrial applications Transportation (FC, ICE)2nd generation Biofuel

H2

BIOMASS +HYDROGEN BIOFUEL

C6H9O4 + eau 5.5 H2 6 -CH2-


The six systems: where are we today ?

Sodium-cooled Fast Reactor

Lead-cooled Fast Reactor

Molten Salt Reactor

Gas-cooled Fast Reactor

Supercritical Water-cooled ReactorVery High Temperature Reactor


VHTR Objectives

• Efficiency of over 50%

• The reference reactor concept has a 600-MWth helium-cooled core

• Estimated by the Roadmap to be deployed in 2020

• Thermal neutron spectrum and a once-through uranium cycle

• Hydrogen production and other process-heat applications (outlet temperatures above 1000°C), it could produce electricity as well


VHTR system today

• Two main projects – NGNP in the US– PBMR in South Africa

• Active collaboration• Cost and acceptance of passive safety ?

– Necessity to add a containment building to existing projects despite no deterministic core meltdown

– Limit the reactor power to a small one• Hydrogen use not so easy, but still interesting for heat processes

– Direct cycle for power conversion system not compatible with heat process

• Still a long way to Very high temperature– No good materials, lifetime very short– Are there still incentives for very high T° uses ?

• Not sustainable


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�Cold�

Cold Plenum

Hot Plenum

PrimarySodium�Hot�

Control Rods

Heat�Exchanger

Steam Generator

Core

SecondarySodium

SFR Objectives

• Cost reduction

• Safety

• Closed fuel cycle system with full TRU recycle for sustainability

• TRU burning and LLFP incineration to reduce environmental burden

• Estimated deployment time: 2015


SFR system today

• Several projects– JSFR in Japan– ASTRID in France– BN800 & BN1200 in Russia– CEFR in China and PFBR in India

• An active collaboration• Hard to switch from GEN III SFR to GEN IV SFR• Competition between building soon and innovate• Enhanced Safety is of first concern

– A fast neutron core is not in its more reactive configuration– Sodium is reactive and opaque

• An incentive to share correctly R&D world wide


GFR Objectives

• Safety• High sustainability with

a closed fuel cycle and full TRU recycle

• Fast- spectrum core• Direct Brayton cycle,

high-efficiency energy conversion



GFR system today

• Interest limited to some countries• A new consistent design• With attractive features

– But a complex primary structure• But mainly paper studies

– Technology to be assessed• Ceramic clad for fuel is a big challenge

– More than 15 year developments ?– Metallic alloy as a backup is also difficult

• Longer term deployment scheduled• Tendency to decrease (optimize) performance for a first construction

– T° < 850°C, breeding ratio, waste transmutation


LFR Objectives

• Fast-neutron spectrum • A full actinide recycle fuel cycle. • Designed for distributed generation of

electricity and other energy products, including hydrogen and potable water.

• LFR system is estimated to be deployable by 2025.


LFR system today

• Waiting for Russia program• Low progress on corrosion

– the main challenge• New design adapted to present know-how

– But reduced performance• Advantage upon SFR not obvious• Often mixed with Accelerator Driven System development


SCWR Objectives

• Links with PWR• Safety• Direct SCW cycle, very

high-efficiency energy conversion ( >44%)

• Direct and Indirect Production of H2



SCWR system today

• Still interesting as an optimized LWR or HWR

• Difficulties to draw a stable core (pressure vessel type) and a stable primary circuit

• Corrosion is also an important issue

• Fast neutron core not possible– Very positive voiding reactivity

effect• R&D concentrates on key points


• The fuel is a circulating liquid mixture of sodium, zirconium, and uranium fluorides.

• Epithermal to thermal neutron spectrum and a closed fuel cycle.

• A full actinide recycle fuel cycle. • The reference plant has a power

level of 1000 MWe. • The MSR is estimated to be

deployable by 2025.

MSR Objectives


MSR system today

• No updated design to comply today safety requirements– First barrier (clad) is missing

• Capabilities to be assessed with a coherent and safe design

• Corrosion/materials issues• Fuel cycle facility cannot be

coupled to the reactor • Fuel cycle to be developed

• More longer term deployment


Contributions to the Generation IV International Forum

VHTR

GFR

SFR

LFR

MSR

SCWR

Japenese Chairmanship since end of 2009 (3 year term)

EURATOM = European Implementing Agent

Generation IV International

ForumChinaChina

RussiaRussiaEuratom


The GIF Management

What are SRPs, SAs, PMBs, PPs, PAs ?

FrameworkAgreement

SystemArrangement

(SA)

ProjectArrangement

(PA)

InstrumentsR&D Plans

SystemResearch Plan

(SRP)

Project Plan(PP)

Technology RoadmapPolicy Group

Reports to

* Technical Director is Chair of the Experts Group

Chair

Chair*

System Steering Committees

Co-Chairs

Project Management Boards

(specific or common projects)

Crosscutting Evaluation

Methodology Groups and Management

Board

Secretariat

Policy TechnicalDirector Director*

NEA, Paris

Co-Chairs

Provides Secretariat forCommunicates closely with

Technical Secretariat

Experts Group

Senior Industry Advisory Panel

Policy Group

Reports to

* Technical Director is Chair of the Experts Group

Chair

Chair*

System Steering Committees

Co-Chairs

Project Management Boards

(specific or common projects)

Crosscutting Evaluation

Methodology Groups and Management

Board

Secretariat

Policy TechnicalDirector Director*

NEA, Paris

Co-Chairs

Provides Secretariat forCommunicates closely with

Technical Secretariat

Experts Group

Senior Industry Advisory Panel


INPRO: an initiative to specify and assess nuclear systems for IAEA member countriesINPROA unique forum for the development of nuclear energy in

IAEA affiliated countries, strengthening the cooperation between Technology “Holders”& “Users”

More than 22 countries• Argentina, Armenia, Brazil, Bulgaria,

Canada, Chile, China, Czech Republic, France, Germany, India, Indonesia, Morocco, Netherlands, Republic of Korea, Pakistan, Russian Federation, South Africa, Spain, Switzerland, Turkey, the European Commission, …


Mission of INPRO

• A forum for experts and policy makers from industrialized and developing countries – To discuss technical, economical, environmental,

proliferation resistance and social aspects of nuclear energy planning;

– To develop tools to analyze on a global, regional and national basis the role and structure of INS required to meet energy demands in a sustainable manner;

– To develop the methodology for assessing and using INS within a set of IAEA recommendations;

– To assist international cooperation for INS development and deployment;

– To pay particular attention to the needs of developing countries


International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Atomic Energy Agency – IAEA

• Focus on – Economic aspects – Societal acceptability issues– And proliferation resistance, nuclear safety, waste management and sustainability issues

• Providing assistance to the user community.

• Phase 1 of INPRO was initiated in 2001• Phase-1A (2003):

– Selection of basic principles, user requirements, criteria and development of a methodology and guidelines for the evaluation of different Innovative Nuclear Energy Systems and recommendations for changes in the infrastructure

• Phase-1B (started in 2003):– 1st Part (2003 – 2004):– Validation and improvement of the Methodology through national and individual case

studies; preparation of a User Manual to perform INS assessments;– 2nd Part (2005 – 2006):– Assessments of Innovative Nuclear Energy Systems using the updated INPRO

methodology.• Phase 2 underway

– Assessment of the methodology on real cases


GNEP – Reliable Fuel Service Model

Expand nuclear energy while preventing spread of sensitive fuel cycle technologyFuel Cycle Nations – Operate both nuclear power plants and fuel cycle facilitiesReactor Nations – Operate only reactors, lease and return fuel

International Centers for fuel servicesInternational Standards for non-proliferation & safeguards

Various Specifications & Processes (waste, technologies…)


GNEP Statement of principles, 2007 (excerpts)Global Nuclear Energy Partnership - a US-DOE proposal

• GNEP is cooperation of those States that share the common vision of the necessity of the expansion of nuclear energy for peaceful purposes worldwide …

• States participating in this cooperation would not give up any rights

• Commitments and international obligations, including IAEA safeguards … will be strictly observed.

• Establish international supply frameworks to enhance reliable, cost-effective fuel services … While reducing the risk of nuclear proliferation by creating a viable alternative to acquisition ofsensitive fuel technologies.

• Take advantage of the best available fuel cycle approaches for the efficient and responsible use of energy and natural resources.• Develop, demonstrate and deploy advanced fast reactors …

• Develop and demonstrate advanced technologies for recycling spent nuclear fuel


Strategic Research Agenda

Open to all European members of the Platform (about 50)


Summary of main results of NEA P&T study (ENC 2005)

0.001

0.01

0.1

1

10Total Cost

Uranium Consumption

TRU Loss

Activity (after 1000 yrs)

Decay Heat (after 50yrs)

Decay Heat (after 200yrs)HLW Volume (+SF)

max. dose (granite)

max. dose (clay)

max. dose (tuff)

Fuel Cycle Cost

1a1b2a3cV1

1a: Once-through cycle as reference.

1b: full LWR park, Pu re-used once

2a: full LWR park, multiple re-use of Pu

3cV1: full fast reactor park and fully closed fuel cycle (Gen IV).

Generation IV and Partitioning & Transmutation impacts


From LWRs to Future Nuclear Energy Systems

• Nuclear energy is a vital component of the world energy mix• Sustainable nuclear energy should be based on fissile material re-

generation– Several thousands years of resources will be so available

• Fast neutron systems can achieve the goal• Future nuclear systems are studied at an international level

(Generation IV Forum, IAEA-INPRO, European SNE-TP …)• Fast Neutrons Systems have been selected worldwide to be

developed by 2040:– SFR, GFR and LFR– Together with two more prospective systems : MSR and SCWR

• This is in indeed vital:– To progress towards a low carbon future– To be more influential on design features and international standards

for future nuclear systems.

Summary and perspectives

generation iv concepts and international frames

Documents