Next Generation Nuclear Reactors - jaif.or.jp · -Nuclear Energy-Safety principles ... • Concepts with breakthroughs ... Light Water Reactors-One technology but two different designs:

WNU - Ottawa 1Jacques BOUCHARD, July 15, 2008

Next Generation Nuclear Reactors

Jacques BOUCHARDCommissariat à l’Energie Atomique

FRANCE


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


Introduction

- Nuclear Energy

- Safety principles

- Economy

- Public acceptance


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


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


Introduction : Economy – capital cost

Nuclear energy :•• High capital investment costsHigh capital investment costs• Long planning horizons• Low Fuel and O&M costs

%


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


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


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


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


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


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


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


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


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)


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.


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


•• 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)


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


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

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The US example


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

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Power Gas Coal Fuel Nuclear

Comparison of European power market prices and operating costs for different type of fuels

oil


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



Westinghouse : AP1000





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


Corium spreading test : CEA - VULCANOMelt spreading phenomena have been extensively investigated

real UO2 with some ZrO2


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


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.


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



Source: General Atomics


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.


High Temperature Reactors : The fuel

Prismatic fuel element with TRISO particles(source: General Atomics)



HTTR (Japan)



HTR 10 (China)


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


PBMR (South Africa)


• 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


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


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


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


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


• 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


• ‘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


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


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


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


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


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.


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


SFR Sodium-Cooled Fast Reactor

The pool design


Phenix


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


� � �� D/ G

Reactor bldg.

Secondary pump

Air cooler

Fuel

Coolers

condenser

OutletHeat

exchangers

FBR Prototype Monju (Japan)

4

DG Bat.


BN 600 (Russia)A 600 MWe plant built at Beloyarsky (Russia)First criticality: 1980; still in operation


SUPERPHENIXA 1200 MWe plant built at Creys-Malville (France)First criticality: 1985; Shutdown: 1997


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


LFR Lead-cooled Fast Reactor


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)


GFR Gas-Cooled Fast Reactor


Generation IV International Forum


The Gen IV Structure


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


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


Signature of the Generation IV Framework Agreement on 28th February 2005 in Washington DC


Charter Signing Ceremony by China and Russia – Paris, 11/06


VHTR SA Signing Ceremony – Paris, 11/06


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”


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.


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


Current Scope of Activities


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


Future Prototypes : VHTR

NGNP ( USA, Idaho)


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

Documents

Next Generation Nuclear Reactors - jaif.or.jp · -Nuclear Energy-Safety principles ... • Concepts with breakthroughs ... Light Water Reactors-One technology but two different designs: