Situação da Geração Termonuclear no Mundo: EUA, Europa€¦ · Situação da Geração Termonuclear no Mundo: EUA, Europa Antonio Gaivão Generation Coordinator GDF Suez Energy

Situação da Geração Termonuclear no Mundo:

EUA, Europa

Antonio GaivãoGeneration Coordinator

GDF Suez Energy Latin America

Em colaboração com:Luc Geraets (GDFSuez)

Yves Crommelynck (GDFSuez)

APINE Workshop Energia Nuclear – Rio de Janeiro 27 Novembro 20082

1. Generation I and Generation II technologies

2. Installed Capacity and Generation

3. Present and announced trends

4. New Evolutionary Reactors; Generation III and III+

5. EPRs in Western Europe

6. AP1000

7. Generation IV: Innovative concepts

8. Fuel Management for Sustainability

INDEX


1. Generation I and Generation II

technologies

Nuclear Power Generation


The first prototypes and research reactors: GENERATION I

1942 - Fermi Pile: first critical chain reaction

1963 – First reactor at Mol in Belgium:BR1 (11MW)

4


Early Prototype

Reactors

Generation I

- Shippingport

- Dresden, Fermi I

- Magnox

Generation II

- LWR-PWR, BWR

- CANDU PHWR

- VVER/RBMK

1950 1960 1970 1980 1990 2000 2010 2020 2030

Generation IV

- Highly Economical

- Enhanced Safety

- Minimal Waste

- Proliferation Resistant

- ABWR

- System 80+

- AP1000; AP600

- EPR

Advanced LWRs

Generation III

Gen I Gen II Gen III Gen IV

Evolutionary

Designs Offering

Improved Economics

Main reactor lines

5

Industrial Expansion

Generation IIII +


GENERATION II :Basic elements of a nuclear power reactor

• Fuel: UO2 (enriched or natural), MOX

• Moderator: Graphite, Water, Heavy Water

• Coolant: Water, He, CO2, air, Na, Pb(-Bi)

• Control rods

• SCRAM system (emergency stop)

• Pressure vessel or pressure tubes

• Confinement building

• Steam generator/alternator

6


Pressurized water reactor (PWR)

7



Conventional islandNuclear island

Nuclear Thermal Mechanical ElectricalEnergy conversion:

Primary

system

Secondary

system



Reactor

• 150 to 250 assemblies with 200 to 300 fuel pins each � 80 to 100 tonnes of uranium

• Negative temperature reactivity coefficient

• Extra emergency stop by injection of boric acid in primary loop

• VVER= Russian PWR, hexagonal fuel structure

Primary Circuit (cooling loop)

• Water under high pressure: above 150 bar (no boiling)

• Maximum water temperature: 325°C

• Vapour fraction controlled by pressurizer

• Heat transfered to secondary system in heat exchangers (Steam Generators)

Secondary system (Steam to turbine)

• not radioactive, under low pressure (70 bar)

9


Lay-out of the primary system of a PWR

10


Reactor Vessel

Vessel� Is a cylinder in MnMo Steel with

hemispherical bottom head and removable top head

� The internal wall is in stainless steel to prevent corrosion

� Is the only component that cannot be replaced. (→→→→ Pressure Vessel Surveillance Programme)

Main functions/characteristics� Support of the core and the mechanism

of the control rod

� Resistance to the high pressure of the water

� Third barrier between the fuel and the environment

11


Steam Generator

� Steam GeneratorIs the “meeting point” between the primary and secondary system. Inside of the steam generator, the hot reactor coolant release the heat to the water of the secondary systems that is transformed is steam.

� Important points� The content of the moisture in the steam

must be as low as possible to prevent damage at the blades of the turbine

� Continuous control of the physical separation between the water of the primary and secondary systems.

12


Boiling water reactor (BWR)

13


Boiling water reactor (BWR)

Reactor:

• 750 assemblies of 90 to 100 fuel pins � 140 tonnes of uranium

• Control rods in the bottom part of the vessel

• 12-15% of the water vaporized in the upper part of the core � less efficient moderation capability

Primary Circuit (water – steam loop)

• Primary cooling circuit under low pressure (75 bar)

• Water temperature in the reactor: 285 °C (boiling)

• Steam dried above the core and then sent to the turbines which are part of the primary circuit

• The primary circuit water contains radioactive nuclides:

� The turbine must be placed in the confinement building and shielded during maintenance

� Associated costs are in equilibrium with the economies made by simpler design

� Most radioactive nuclides have short half-lives � the turbine hall can be accessed quite soon after reactor shut-down

� The most present radio-isotope is N-16 with a half life of 7 seconds

14


Gas Reactor: MAGNOX, UNGG

Origin: MAGNOX (UK), UNGG (France), etc.� Graphite moderated

� Cooled by CO2

� Fuel: natural uranium in metallic form, in a cladding of magnesium alloy

CO2 replaced He (first choice) : less expensive

Graphite as moderator� Good slowing-down properties and small neutron absorption

� Large dimensions needed for optimal moderation � very large reactor cores

� The graphite degrades due to the neutron irradiation

The accumulated energy (Wigner energy) must be released by a tempering of the graphite matrix

15


Advanced Gas Reactor (AGR)

16


Advanced Gas Reactor (AGR)

Goal: higher thermal efficiency (power)

� Higher fuel temperatures

� MAGNOX metallic uranium has bad swelling properties � UO2 pellets as fuel � pellets in stainless steel cladding � slightly enriched fuel up to 2.5-3.5%.

Coolant CO2

� Circulates through the core

� Reaches temperatures up to 650°C

� Goes by tubes to the steam generator located outside the core (but inside the concrete and confinement)

Control rods penetrate the moderator

Second scram system: nitrogen injection in the core coolant

AGRs not economically competitive with PWRs and BWRs

17


Pressurized Heavy Water Reactor (PHWR)

18


Pressurized Heavy Water Reactor (PHWR)

• The most well-known design: CANDU (Canada)

• Fuel: natural uranium dioxide

• Moderator: Heavy Water in a big pool (calandria)

• Primary Coolant: Heavy Water under high pressure circulating in tubes traversing the calandria which contain the fuel

• Maximum Water temperature = 290 °C

• Primary coolant generates steam in secondary system to drive the turbines

• The design with pressurized tubes allows the refueling of the reactor core during operation

• One assembly of 37 fuel pins and half a meter length (fuel pellet in a cladding of zircalloy); one channel is filled with 12 assemblies in a row

• The control rods penetrate the core vertically

• A second emergency system consists of adding gadolinium to the moderator

19


Light Water Graphite Reactor (RBMK)

• Russian design first foreseen to produce military plutonium

• Later modified for electricity production

• The core consists of pressurized tubes of 7m length which traverse the graphite (moderator)

• Cooling: boiling water at a maximum temperature of 290°C, as in a BWR.

• The fuel is slightly enriched uranium oxide put in assemblies of 3.5m length.

• Inconvenience of the design: moderation largely due to the graphite.

In case of increase of the boiling and hence the bubble fraction, cooling capacity significantly reduced with no feedback effect on the core reactivity.

On top of that, neutron absorption in the coolant is also reduced => positive reactivity coefficient

20


Light Water Graphite Reactor (RBMK)

21

• Originally designed for the production of fissile material from

fertile isotopes = breeding

� 1 neutron to keep the chain reaction going

� 1 neutron for the conversion of a fertile nuclide into a fissile nuclide

� fast reactor with Pu

• No dedicated moderation, although some results from the fact that the fuel is in the form of oxides or carbides

U-235 Pu-239

n thermal 2.07 2.09

n fast 2.18 2.74


Fast Breeder Reactors (FBR)

22

• Coolant (liquid Na) is not a moderator:

Advantages

�Good heat transfer coefficient, compact core

�High boiling point under atmospheric pressure: 900 °C

�Hydraulic properties close to those of water

�Non-corrosive for most steels if the oxygen content remains low

� Disadvantages

�Large affinity of sodium for oxygen: all core reloading must be done under inert atmosphere

�Sodium reacts exothermically with water

�Sodium becomes highly radioactive-> intermediate cooling system needed

�Relatively large positive void coefficient


2. Installed Capacity

and Generation



Present Energy Scene

Final Energy Consumption

Kg ep/year ihnabitant

Share of Electricity in total ~18%

Share of nuclear in Electrivcity ~17%


Installed Capacity and Generation


Total 435 NPPs �� 364,000 MWe (252 PWRs; 93 BWRs)

Nuclear Power Plants in the World


Installed Capacity and Generation

Nuclear Power Plants in operation

367.684440Total

29.04759Others <4.000MW

338.637381Sub total

224.8846Taiwan

575.7287Belgium

36.5879China

237.5849Spain

528.85710Sweden

1911.85223UK

1512.08017Canada

5113.16815Ucrania

3816.84020Corea

3220.30317Germany

1621.74331Russia

2947.70055Japan

7763.47359France

2097.838103USA

%MW-

Sharein mix

(generation)

Installedpower

N°ofunitsCountry

0,0

10,0

20,0

30,0

40,0

50,0

60,0

PWR

VVER

BWR PHWR

CANDU

GCR,

AGR,

MAGNOX

LWGR

(RMBK)

FBR

Share (%) of reactors in operation by type


Nuclear Generation: Historical Perspective

Nuclear plants installation stagnates for 20 years by cause of:• Rise of anti-nuclear political conscience nourished by the spectrum of military use;

• High adverse sensitivity of public opinion, after TMI (1979) and Chernobyl (1986) accidents;

• Deep transformations in Eastern Europe countries political order;

• Recession period for mature economies, with volatile long term planning of electricity needs;

• Deregulation of the electricity sector, in the direction of privatization and market driven models;

• Availability of ready to use primary energy alternatives for new power generation facilities: Natural gas and coal, with short construction periods;

• In countries where the potential exists, hydro electricity is a must;

• Promises (and research efforts) of energy alternatives (renewable: solar, wind, biomass)

Nevertheless, nuclear generation contribution increased since 1990 due to:• Significant increase of average availabilityincrease of average availabilityincrease of average availabilityincrease of average availability and capacity factor of the nuclear plants, as result of improved operation (reliability); outage management (reduction of outage time) and internationalcooperation (quality management) through the WANO (World Association of Nuclear Operators, created in 1986)and the AIEA;

• Increase of the unit powerIncrease of the unit powerIncrease of the unit powerIncrease of the unit power output (+5 to 10%), by retrofitting of new equipment and use of the design reserve margins, after due certification (cost effective upgrades <200 USD/kW) .




55

60

65

70

75

80

85

90

95

80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02

Ca

pa

cit

y F

ac

tor

(%)


Increase in average capability of plants in USA (103)

(Corresponds to + 30.000 MW in 20 years)

91,9


3. Present and Announced Trends



• Continuation of nuclear energy contribution

Life extension of existing plants from original 30 years to up to 60 years Certification of many existing NPP (second generation) for

• Plans for construction of new reactors:

US and Canada: Future replacement of existing capacity / marginal increaseNuclear Power 2010 initiative (by DOE),Intense regulatory activity regarding new site licensing procedures ESP (early site permit)and COL (combined operation license)

Europe and CEI: Future replacement of existing capacity (France, Finland, eastern Europe)Maintain of retrieve decision in others20% reduction of overall installed power

Note: Kyoto CO2 reduction burden shares: France, Finland = 0; Germany = -21%)

Asia and Pacific: Important contribution to growth of electrical powerJapan, Corea, China, India, Pakistan, Indonesia, Corea DPR

• New developments of the nuclear industry � (Generation III and IV reactors)

Present and Announced Trends


G8 on July 8, 2008

� Expand development of nuclear power

� Utmost importance of non proliferation

� 29 countries willing to introduce nuclear power

� Japan (40% nuclear by 2030), US and Russia to expand capacity


Nuclear power generation: Zoom on Europe

• 16 out of 27 countries with nuclear energy

• Future of nuclear energy is not clear at national level :

� 4 countries decided to phase out (Belgium, Germany, Italy and Sweden)

� Italy revisiting its choice

� Austria strongly opposed

� Netherlands has extended the lifetime of its NPP by 20 years (2033)

� One new NPP in operation in 2007 (Romania)

� United Kingdom in the move

� (At least) 6 countries decided to build new NPPs

Finland (1 EPR in progress + 1 ) France (1 EPR)

Slovakia (2 VVER440) Romania (2 Candu)

Bulgaria (2 VVER1000) United Kingdom (TBD)

• European Union very cautious, but recent initiatives in the nuclear field :

� European Nuclear Energy Forum

� High Level Group on Nuclear Safety and Waste Management

� Sustainable Nuclear Energy Technology Platform


New Nuclear Power Plants

450030000Turkey

2850395019591Iran

00006921Argentina

001245100Brasil

00950100Ucrania

00257045151Canada

0014782128661Japan

001600100Finland

58.1457341.4723917.43123Total

9.6601330015461Others

484856041172381688522Sub total

200020000Indonesia

1316024003.6388India

00002.7002Taiwan

1500019800081.9002China

0095019501Corea DPR

009200800Corea

9375892513.6004Russia

160010000France

00001.0651USA

MW-MW-MW-

ProposedAt Project stageUnder constructionCountry


Nuclear power is part of the solution

• Important factor of stability

�Security of supply

� Diversity of reliable uranium supply sources

� No link with the volatility of fuel prices

�Stable, predictable and competitive costs

�Major contribution to the reduction of greenhouse gas emissions

• Saving of fossil fuels

• Rational use of primary natural resources

• CO2 - free

�countries with nuclear and hydro obtain the best results in CO2 emissions

�500 million tons saved each year in Europe, as much as

� the Kyoto target for the EU (8 % below the 1990 level)

� the emissions from about 3/4 of all the private cars in the EU


4. New Evolutionary Reactors: Generation III and III+



Early Prototype

Reactors

Generation I

- Shippingport

- Dresden, Fermi I

- Magnox

Generation II

- LWR-PWR, BWR

- CANDU PHWR

- VVER/RBMK

1950 1960 1970 1980 1990 2000 2010 2020 2030

Generation IV

- Highly Economical

- Enhanced Safety

- Minimal Waste

- Proliferation Resistant

- ABWR

- System 80+

- AP600

- EPR

Advanced LWRs

Generation III

Gen I Gen II Gen III Gen IV

Evolutionary

Designs Offering

Improved Economics

Main reactor lines

38

Industrial Expansion

Generation IIII +


Large Evolutionary Reactors: Generation III

• Concept

Extrapolation of second generation models (unit power ~1500MW; no major technologic step)

Integration of operation return of experience (including major incidents)

Improved intrinsic safety (passive systems), simplification of auxiliary systems

Higher efficiency and availability with longer fuel charges

Use of proven technologies (fuel, primary components, turbo group, I&C)

• Products: EPR 1500MW (European Project Reactor) by Framatome – Siemens – EDF

AP 1000MW by Westinghouse

ABWR 1350MW by GE Nuclear Energy

System 80+ (CE > ABB > Westinghouse BNFL)

CANDU 9

KNGR, VVER-91

• Projects: 1 EPR in Finland, Olkiluoto 3, for TVO

1 EPR in France for EDF

4 ABWR built (in service since 1995)


GENERATION III +: Evolutionary concepts

• Passive safety components

� Natural circulation core cooling

� Convective cooling of safety containment

� Heat removal by radiation

• AP1000, ESBWR, SWR-1000, PBMR, GT-MHR,

• APWR, EP-1000, AC-600, MS-600, V-407, V-392, JSBWR,

• JSPWR, HSBWR, CANDU-6, CANDU-9, AHWR, ...

40


Inovative Small and Medium Reactors (SMR) – Generation III+

2nd Latin American Energy Integration CongressSantiago do Chile 26 October 2005

ChinaINETPebble Bed ModularHTR160HTR-PM

Pre-certifiedSouth AfricaEskomPebble Bed ModularHTR165PBMR

Pre-certifiedUSA / Russia

General Atomics / Minatom

Gas Turbine ModularHeliumHTR285GTMHR

High Temperature Gas Reactor

RussiaOKBMIPWR35KLT 40

Rep CoreaKAERISystem Integrated ModularIPWR100SMART

JapanJAERIIPWR100MRX

ArgentinaCNEA & INVAPModularIPWR300CAREM 300

FranceTechnicatomeIPWR300NP 300

Pre-certifiedUSAWestinghouse BNFLIntern. Reactor Inovative &

SecureIPWR335IRIS 300

Integrated Presurized Water Reactor

Certification by NRC

CountryDeveloperCharacteristicTypePower

MWName

Inovative Small and Medium Reactors:

Generation III+


5. EPRs in Western Europe



Evolutionary Pressurized Reactor (EPR)

43


Reactor

vessel

Turbine buildingReactor building

4 safety buildings4 x 100%

EPR: Active safety system fourfold redundant

44


EPR: Double containment

– concrete –– steel –– concrete –

resists the impact of a large airplane

45


EPR: Passively cooled ‘Core catcher’

Cooling water

46


EPR’s in Western Europe

47


Olkiluoto EPR (September 2008)

48


5. AP1000



AP1000: Advanced Passive PWR1117 MWe (Westinghouse – USA)

50


AP1000: Passive safety systems:less components

51


high-pressure cooling (nat. circ.)

medium-pressure cooling (nat. circ.)

low-pressure cooling(gravity)

Heat exchanger(natural circulation)

Passive emergency cooling of safety systems

52


AP1000: Passive emergency cooling of containment

53


Generation III Generation IIIGeneration III Generation III++

ABWR EPR AP1000 ESBWR PBMR HTR-PM

Type BWR PWR PWR BWR HTR HTR

Generation III III III+ III+ III+ III+

Power 1350 1600 1150 1550 165 190

US certification yes no a) yes no b) no no

In use 3 0 0 0 0 0

In construction 3 1 0 0 0 0

Dwell time 72 hour 30 min 72 hour 24 hour ∞ ∞

Core melt frequency (1/year) 2⋅10-7 1.3⋅10-6 4⋅10-7 3⋅10-8 0 0

‘core catcher’ no yes <24 hour <24 hour not needed not needed

Construction time (yr) 4 4 3 3 2 ?

Technical lifetime (yr) 60 60 60 60 ? ?

GEN III and III+: Overview


6. Generation IV:

Innovative concepts



• International initiatives for joint development:

IV Generation International Forum (GIF)

International Project on Inovative

Nuclear Reactors and Fuel Cycles (INPRO)

• Targets and criteria:

Economic competitiveness

Safety and reliability

Non proliferation (minimum waste; full recycle of burnt fuel (*))

Multiple use: Electrical power, industrial heat, desalination, hydrogen vector

• Extension of primary energy reserves

Fast Breeder Reactors (*), capable of burning the Uranium fission sub product Pu,

would multiply by 60 or 100 the energy generation capability of the present fuels.

Inovative Large Reactors: Generation IV


Sustainability

� Long-term availability of fuel and effective utilization of fuel

� minimizing the amount and toxicity of discharged fuel and other high level radioactive products

� increasing the proliferation resistance of the fuel cycle

Safety & Reliability

� Very low likelihood and degree of reactor core damage by means of additional passive features and increased intrinsic safety,

Economics

� capital costs

� O&M costs

� fuel cycle costs,

� decommissioning & decontamination costs,

� overall project duration : construction schedule, capacity factor, life time

57


Target Criteria


6 concepts selected for evaluation in GIF IV

Feasibility Performance

Sodium Cooled Fast Reactor SFR

Very High Temperature Reactor VHTR

Supercritical Water Cooler Reactor SCWR

Lead-Alloy Cooled Reactor LFR

Gas-Cooled Fast Reactor GFR

Molten Salt Reactor MSR

Therm - Fast / Open - Closed

Fast / Open Fuel Cycle

Fast / Closed Cycle

Thermal / Open Cycle

Therm / Closed

Fast / Closed Cycle



Generation IV nuclear systems

Sodium Fast Reactor

Lead Fast Reactor

Molten Salt Reactor (fast?)

Gas Fast Reactor

Supercritical Water-cooled

Reactor

Very High Temperature Reactor

59


GEN IV proposed designs

neutron spectrum

(fast/ thermal)

coolantTemp(°C)

pressure* fuelfuel

cyclesize(s)(MWe)

uses

GFR Fast helium 850 High U-238closed, on site

288electricity

& hydrogen

LFR Fast Pb-Bi 550-800 Low U-238closed, regional

50-150**300-400

1200

electricity& hydrogen

MSR epithermalfluoride

salts700-800 Low UF in salt closed 1000

electricity& hydrogen

SFR Fast sodium 550 LowU-238 &

MOXclosed

150-500500-1500

electricity

SCWRthermal or

fastwater 510-550 Very high UO2

open (thermal)closed (fast)

1500 electricity

VHTR thermal helium 1000 HighUO2

prism or pebbles

open 250hydrogen

& electricity

60


7. Fuel Management for Sustainability



Reserves

FRONT ENDNatural U supply evolution

Estimation of the resources

Reasonably Assured Resources

(RAR) – price ranges 1 and 2

62November 2008


• Uranium Mining and Extraction �(~50% of demand)

• Uranium 235 Enrichment

Ultra centrifugation technology dominates

Important over capacity available (i.e. in Russia)

• Other sourcesSupply from stocks

Recovery of tails (spent fuel)

Conversion of HEU to LEU as per 1994 agreement (USA/Russia), until 2013

ton/year35.000Total production

4%Others

3%USA

8%Central Africa

9%South Africa

20%CEI

21%Australia

35%Canada

ShareCountry/ Region

Fuel Front End: Sensitive to Proliferation


Europe USA

FRONT ENDPWR Fuel Manufacturers (2007)

Timeframe : From mining to core loading : 27 months

64November 2008


Source: Julian Steyn, EDI, Nuclear Engineering International Sept 2007

World Conversion supply and demand (thousand tonnes U as UF6)

Supplier 2007 2010 2015

Cameco (Canada & UK) 13,7 15,5 15,5

AREVA (France) 14 14 15

ConverDyn (US) 12 14 18

Rosatom (Russia) 5 5,5 10

CNNC (China) 1,5 2,5 2,5

UF6 inventories 20,1 20,8 11

Total supply 66,3 72,3 72

Requirements (ERI ) 59 62-65 67-77

FRONT ENDConversion – world capacities

65


Nuclear energy production in the future(2030-2100)?

• Generation II(I): spent fuel waste

• Uranium resource issue

Sustainability of

nuclear energy production


• Reprocessing for MOX (Mixed Oxides) fuel

Adopted by: UK, France, Japan, Russia (partially) and also China and India.

• Waste (HLW) Storage

Intermediate solutions available for nuclear waste storage

Long term solutions in R&D (re-use in breeder reactors or deep geological disposal)

• Manageable volumes1kg of natural Uranium ~ 20.000 kg of coal, with present open cycle burning rate

16 t of processed Uranio = 1.600.00 ton Coal (x 100.000)

1000 MW LWR 25-30 tonnes of spent fuel/year 3 m³/y of vitrified waste

• Security and Safety

Certification of technologies by regulatory agences

AIEA – Consolidation of authority for monitoring, control and certification

Common denominator for safety rules and standards

Non proliferation concern – International and National Safegards / Physical protection

Control / Accounting and Monitoring of fuel cycle materials

Fuel Back End: Sensitive to Proliferation

Thank you

[email protected]

Documents

Situação da Geração Termonuclear no Mundo: EUA, Europa€¦ · Situação da Geração Termonuclear no Mundo: EUA, Europa Antonio Gaivão Generation Coordinator GDF Suez Energy