1 24/04/2014 ENV-2A82/ENV-2A82K Low Carbon Energy 2010 - 11 NUCLEAR POWER

110/04/23

ENV-2A82/ENV-2A82KLow Carbon Energy

2010 - 11

NUCLEAR POWER

http://www2.env.uea.ac.uk/energy/env-2a82/env-2a82.htmhttp://www2.env.uea.ac.uk/energy/energy.htm

N.K. Tovey (杜伟贤 ) M.A, PhD, CEng, MICE, CEnv Н.К.Тови М.А., д-р технических наук

Energy Science Director CRed Project

HSBC Director of Low Carbon Innovation

http://www2.env.uea.ac.uk/energy/env-2a82/env-2a82.htm

http://www2.env.uea.ac.uk/energy/energy.htm

Kung Hei Fat Choi !Kung Hei Fat Choi !

Gong Xi Fa Cai !Gong Xi Fa Cai !

310/04/23

NUCLEAR POWERBackground Introduction 1. Nature of Radioactivity

a. Structure of the Atomb. Radioactive Emissionsc. Half Life of Elementsd. Fissione. Fusionf. Chain Reactionsg. Fertile Materials

2. Fission Reactors – reduced coverage in 2011Not Covered in 2011 but notes from previous years in handout

3. Nuclear Fuel Cycle4. Fusion Reactors5. Radiation and Man

410/04/23

0

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14000

1955 1965 1975 1985 1995 2005 2015 2025 2035

Inst

all

ed C

ap

aci

ty (

MW

)New Build ?

ProjectedActual

New Build Assumes 10 new nuclear power

stations are completed (one each year from

2019).

NUCLEAR POWER in the UK

Generation 1: MAGNOX: (Anglo-French design) four reactors ( two stations) still operating on extended lives of 42 and 40 years

Generation 2a: Advanced Gas Cooled reactors (unique UK design) – most efficient nuclear power stations ever built - 14 reactors operating.

Generation 2b: Pressurised Water Reactor – most common reactor Worldwide. UK has just one Reactor 1188MW at Sizewell B.

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bil

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nuclear new nuclear coal

new coal oil renewablesgas medium renewables high renewables

Our looming over-dependence on gas for electricity generation

We need an integrated energy supply which is diverse and secure.

We need to take Energy out of Party Politics.!

610/04/23

Carbon Dioxide Emissions

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1990 1995 2000 2005 2010 2015 2020 2025

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s C

O2

Actual

Business as Usual

Energy Efficiency

The Gas Scenario

Assumes all new non-renewable generation is from gas.

Replacements for ageing plant

Additions to deal with demand changes

Assumes 10.4% renewables by 2010

25% renewables by 2025

Energy Efficiency – consumption capped at 400 TWh by 2010

But 68% growth in gas demand (compared to 2002)

Business as Usual

257% increase in gas consumption ( compared to 2002)

Electricity Options for the Future

Gas Consumption

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1990 1995 2000 2005 2010 2015 2020 2025

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Business as Usual

Energy Efficiency

710/04/23

Energy Efficiency Scenario

Other Options

Some New Nuclear needed by 2025 if CO2 levels are to fall significantly and

excessive gas demand is to be avoided

Business as Usual Scenario

New Nuclear is required even to reduce back to 1990 levels


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ActualGasNuclearCoal40:20:40 Mix


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ActualGasNuclearCoal40:20:40 Mix

25% Renewables by 2025

• 20000 MW Wind

• 16000 MW Other Renewables inc. Tidal, hydro, biomass etc.

Alternative Electricity Options for the Future

Combined heat and power can also be used with Nuclear Power

To District Heat Main ~ 90oC

Boiler

Heat Exchanger

e.g. Switzerland, Sweden, RussiaNuclear Power can be used solely as a source of heat

e.g. some cities in Russia - Novosibirsk

910/04/23

1. NATURE OF RADIOACTIVITY (1)

Structure of Atoms.• Matter is composed of atoms which consist

primarily of a nucleus of:– positively charged PROTONS – and (electrically neutral) NEUTRONS.

• The nucleus is surrounded by a cloud of negatively charged ELECTRONS which balance the charge from the PROTONS.

• PROTONS and NEUTRONS have approximately the same mass

• ELECTRONS are about 0.0005 times the mass of the PROTON.

• A NUCLEON refers to either a PROTON or a NEUTRON

+++

3p

4n

Lithium Atom

3 Protons 4 Neutrons

1010/04/23

1. NATURE OF RADIOACTIVITY (2)Structure of Atoms.

• Elements are characterized by the number of PROTONS present – HYDROGEN nucleus has 1 PROTON – HELIUM has 2 PROTONS– OXYGEN has 8 PROTONS – URANIUM has 92 PROTONS.

• Number of PROTONS is the ATOMIC NUMBER (Z)

• N denotes the number of NEUTRONS.

• The number of neutrons present in any element varies.

• 3 isotopes of hydrogen all with 1 PROTON:-– HYDROGEN itself with NO NEUTRONS– DEUTERIUM (heavy hydrogen) with 1 NEUTRON– TRITIUM with 2 NEUTRONS.

• only TRITIUM is radioactive.

• Elements up to Z = 82 (Lead) have at least one isotope which is stable

Symbol DSymbol T

1110/04/23

1. NATURE OF RADIOACTIVITY (3)Structure of Atoms.

• URANIUM has two main ISOTOPES

• 235U which is present in concentrations of 0.7% in naturally occurring URANIUM

• 238U which is 99.3% of naturally occurring URANIUM.

• Some Nuclear Reactors use Uranium at the naturally occurring concentration of 0.7% - e.g. MAGNOX and CANDU

• Most require some enrichment to around 2.5% - 5%

• Enrichment is energy intensive if using gas diffusion technology, but relatively efficient with centrifuge technology.

• Some demonstration reactors use enrichment at around 93%.

1210/04/23

Radioactive emissions.• FOUR types of radiation:-

• 1) ALPHA particles ()- large particles consisting of 2 PROTONS and 2 NEUTRONS

the nucleus of a HELIUM atom.

• 2) BETA particles (β) which are ELECTRONS

• 3) GAMMA - RAYS. ()– Arise when the kinetic energy of Alpha and Beta particles is lost

passing through the electron clouds of atoms. Some energy is used to break chemical bonds while some is converted into GAMMA -RAYS.

• 4) X - RAYS. – Alpha and Beta particles, and gamma-rays may temporarily

dislodge ELECTRONS from their normal orbits. As the electrons jump back they emit X-Rays which are characteristic of the element which has been excited.

1. NATURE OF RADIOACTIVITY (4)

1310/04/23

NATURE OF RADIOACTIVITY (5)

- particles are stopped by a thin sheet of paper

β – particles are stopped by ~ 3mm aluminium

- rays CANNOT be stopped – they can be attenuated to safe limits using thick Lead and/or concrete

β

1410/04/23

U23592

Radioactive emissions.

• UNSTABLE nuclei emit Alpha or Beta particles

• If an ALPHA particle is emitted, the new element will have an ATOMIC NUMBER two less than the original.

U23592


• If an ELECTRON is emitted as a result of a NEUTRON transmuting into a PROTON, an isotope of the element ONE HIGHER in the PERIODIC TABLE will result.

Th23190

He42

Np23593

e

1510/04/23

Radioactive emissions.• 235U consisting of 92 PROTONS and 143 NEUTRONS is one

of SIX isotopes of URANIUM

• decays as follows:-


URANIUM

235Ualpha

THORIUM

231ThPROTACTINIUM

231PaACTINIUM

227Ac

• Thereafter the ACTINIUM - 227 decays by further alpha and beta particle emissions to LEAD - 207 (207Pb) which is stable.

• Two other naturally occurring radioactive decay series exist. One beginning with 238U, and the other with 232Th.

• Both also decay to stable (but different) isotopes of LEAD.

beta alpha

1610/04/23

HALF LIFE.

• Time taken for half the remaining atoms of an element to undergo their first decay e.g:-

• 238U 4.5 billion years • 235U 0.7 billion years • 232Th 14 billion years

• All of the daughter products in the respective decay series have much shorter half - lives some as short as 10-7 seconds.

• When 10 half-lives have expired, - the remaining number of atoms is less than 0.1% of the original.

• 20 half lives - the remaining number of atoms is less than one millionth of the original– From a Radiological Point of View which is the most

significant to man?– SHORT : INTERMEDIATE; or LONG HALF LIFE??


1710/04/23

HALF LIFE.

From a radiological hazard point of view

• short half lives - up to say 6 months have intense radiation, but

• decay quite rapidly. Krypton-87 (half life 1.8 hours)- emitted from some gas cooled reactors - the radioactivity after 36 hours is insignificant. <0.000001 of original

• For long half lives - the radiation doses are small, and also of little consequence

• For intermediate half lives - these are the problem - e.g. Strontium -90

• has a half life of about 30 years which means it has a relatively high radiation, and does not decay that quickly.

• Radiation decreases to 30% over 90 years


1810/04/23

This reaction is one of several which might take place. In some cases, 3 daughter products are produced.

n

n

n

140Cs

93Rb235U

Some very heavy UNSTABLE elements exhibit FISSION e.g. 235U

NATURE OF RADIOACTIVITY (10): Fission

1910/04/23

• FISSION• Nucleus breaks down into two or three fragments

accompanied by a few free neutrons and the release of very large quantities of energy.

• Free neutrons are available for further FISSION reactions

• Fragments from the fission process usually have an atomic mass number (i.e. N+Z) close to that of iron.

• Elements which undergo FISSION following capture of a neutron such as URANIUM - 235 are known as FISSILE.

• All Nuclear Power Plants currently exploit FISSION reactions,

• FISSION of 1 kg of URANIUM produces as much energy as burning 3000 tonnes of coal.


2010/04/23

n

4He 2H

3H

Deuterium

Tritium

Deuterium – Tritium fusion

(3.5 MeV)

(14.1 MeV) In each reaction 17.6 MeV is liberated or 2.8 picoJoules (2.8 * 10-15J)

Fusion of light elements e.g. DEUTERIUM and TRITIUM produces even greater quantities of energy per nucleon are released.

NATURE OF RADIOACTIVITY (12): Fusion

21

1) The energy released per nucleon in fusion reaction is much greater than the corresponding fission reaction.2) In fission there is no single fission product but a broad range as indicated.

NATURE OF RADIOACTIVITY (13): Binding Energy

0 50 100 150 200 250 Atomic Mass Number

-2

-4

-6

-8

-10

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ding

Ene

rgy

per

nuc

leon

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eV]

Iron 56

Uranium 235Range of Fission

Products

Fusion Energy release per

nucleon

Fission Energy release per

nucleon

1 MeV per nucleon is equivalent to 96.5 TJ per kg

Redrawn from 6th report on Environmental Pollution – Cmnd. 6618 - 1976

2210/04/23

• Developments at the JET facility in Oxfordshire have achieved the break even point.

• After much delay, Next facility (ITER) is now being built in Cadarache in France – completion 2019 – 2020?

• One or two demonstration commercial reactors in 2030s perhaps

• Commercial deployment of fusion from about 2040 onwards

• No radioactive waste from fuel

• Limited radioactivity in power plant itself

• 8 litres of tap water sufficient for all energy needs of one individual for whole of life at a consumption rate comparable to that in UK.

• Sufficient resources for 1 – 10 million years

NATURE OF RADIOACTIVITY (14): Fusion

2310/04/23

n

n

n235U

n

n

n

235

U

Slow neutron

Slow neutronfast neutron

fast neutron

Fast Neutrons are unsuitable for sustaining further reactions

NATURE OF RADIOACTIVITY (15): Chain Reactions

2410/04/23

• CHAIN REACTIONS• FISSION of URANIUM - 235 yields 2 - 3 free neutrons.

• If exactly ONE of these triggers a further FISSION, then a chain reaction occurs, and continuous power can be generated.

• UNLESS DESIGNED CAREFULLY, THE FREE NEUTRONS WILL BE LOST AND THE CHAIN REACTION WILL STOP. - New 3rd Generation Reactors incorporate a neutron reflector to minimise loss

• IF MORE THAN ONE NEUTRON CREATES A NEW FISSION THE REACTION WOULD BE SUPER-CRITICAL

(or in layman's terms a bomb would have been created).


2510/04/23

• CHAIN REACTIONS• IT IS VERY DIFFICULT TO SUSTAIN A CHAIN

REACTION, • Most Neutrons are moving too fast

• TO CREATE A BOMB, THE URANIUM - 235 MUST BE HIGHLY ENRICHED > 93%,

• Normal Uranium is only 0.7% U235

• Material must be LARGER THAN A CRITICAL SIZE and SHAPE OTHERWISE NEUTRONS ARE LOST.

• Atomic Bombs are made by using conventional explosive to bring two sub-critical masses of FISSILE material together for sufficient time for a SUPER-CRITICAL reaction to take place.

• NUCLEAR POWER PLANTS CANNOT EXPLODE LIKE AN ATOMIC BOMB.


2610/04/23

• FERTILE MATERIALS• Some elements like URANIUM - 238 are not FISSILE, but

can transmute:-

n

238U

fast neutron

239U

238UUranium - 238

239UUranium - 239

+n

ee

239NpNeptunium - 239

239PuPlutonium - 239

beta beta

239Np239Pu

PLUTONIUM - 239 is FISSILE and may be used in place of URANIUM - 235.

Materials which can be converted into FISSILE materials are FERTILE.

Nature of Radioactivity (18): Fertile Materials

2710/04/23

FERTILE MATERIALS• URANIUM - 238 is FERTILE as is THORIUM - 232

which can be transmuted into URANIUM - 233.

• Naturally occurring URANIUM consists of 99.3% 238U which is FERTILE and NOT FISSILE, and 0.7% of 235U which is FISSILE. Normal reactors primarily use the FISSILE properties of 235U.

• In natural form, URANIUM CANNOT sustain a chain reaction: free neutrons are travelling fast to successfully cause another FISSION, or are lost to the surrounds.

• MODERATORS are thus needed to slow down/and or reflect the neutrons in a normal FISSION REACTOR.

• The Resource Base of 235U is only decades

• But using a Breeder Reactor Plutonium can be produced from non-fissile 238U producing 239Pu and extending the resource base by a factor of 50+


28

n

n

n235U

n

n

n

235

U

fast neutron

Slow neutronfast neutron

fast neutron

n

Fast Neutrons are unsuitable for sustaining further reactions

NATURE OF RADIOACTIVITY (21): Chain Reactions

Slow neutron

n

Insert a moderator to slow down neutrons

Sustaining a reaction in a Nuclear Power Station

29

NUCLEAR POWER

Background Introduction1. Nature of Radioactivity2. Fission Reactors

a) General Introductionb) MAGNOX Reactorsc) AGR Reactorsd) CANDU Reactorse) PWRsf) BWRsg) RMBK/ LWGRsh) FBRsi) Generation 3 Reactorsj) Generation 3+ Reactors

3. Nuclear Fuel Cycle4. Fusion Reactors5. Radiation and Man

3010/04/23

FISSION REACTORS CONSIST OF:- i) a FISSILE component in the fuel

ii) a MODERATOR

iii) a COOLANT to take the heat to its point of use.

The fuel elements vary between different Reactors

• Some reactors use unenriched URANIUM – i.e. the 235U in fuel elements is at 0.7% of fuel

– e.g. MAGNOX and CANDU reactors,

• ADVANCED GAS COOLED REACTOR (AGR) uses 2.5 – 2.8% enrichment

• PRESSURISED WATER REACTOR (PWR) and BOILING WATER REACTOR (BWR) use around 3.5 – 4% enrichment.

• RMBK (Russian Rector of Chernobyl fame) uses ~2% enrichment

• Some experimental reactors - e.g. High Temperature Reactors (HTR) use

highly enriched URANIUM (>90%) i.e. weapons grade.

FISSION REACTORS (1):

3110/04/23

FISSION REACTORS (2): Fuel Elements

PWR fuel assembly:

UO2 pellets loaded into fuel pins of zirconium each ~ 3 m long in bundles of ~200

Magnox fuel rod:

Natural Uranium metal bar approx 35mm diameter and 1m long in a fuel cladding made of MagNox.

AGR fuel assembly:

UO2 pellets loaded into fuel pins of stainless steel each ~ 1 m long in bundles of 36.

Whole assembly in a graphite cylinder

Burnable poison

3210/04/23

• No need for the extensive coal handling plant.

• In the UK, all the nuclear power stations are sited on the coast so there is no need for cooling towers.

• Land area required is smaller than for coal fired plant.

• In most reactors there are three fluid circuits:-

1) The reactor coolant circuit

2) The steam cycle

3) The cooling water cycle.

• ONLY the REACTOR COOLANT will become radioactive

• The cooling water is passed through the station at a rate of tens of millions of litres of water and hour, and the outlet temperature is raised by around 10oC.


3310/04/23

REACTOR TYPES – summary 1

• MAGNOX - Original British Design named after the magnesium alloy used as fuel cladding. Four reactors of this type were built in France, One in each of Italy, Spain and Japan. 26 units were built in UK.

• They are only in use now in UK. All MAGNOX Reactors have now closed except the two at Oldbury and two at Wylfa. Oldbury was scheduled to close in December 2008 but is still operating at full power. Wylfa is also operating beyond its scheduled closure of December 2010.

• AGR - ADVANCED GAS COOLED REACTOR - solely British design. 14 units are in use. The original demonstration Windscale AGR is now being decommissioned. The last two stations Heysham II and Torness (both with two reactors), were constructed to time and have operated to expectations. Most efficient reactors yet built in terms of utility of fuel.


3410/04/23

REACTOR TYPES - summary• PWR - Originally an American design of

PRESSURIZED WATER REACTOR (also known as a Light Water Reactor LWR). Now most common reactor.-

• BWR - BOILING WATER REACTOR - a derivative of the PWR in which the coolant is allowed to boil in the reactor itself. Second most common reactor in use.

• CANDU - A reactor named initially after CANadian DeUterium moderated reactor (hence CANDU), alternatively known as PHWR (pressurized heavy water reactor). 41 currently in use.

• RMBK - LIGHT WATER GRAPHITE MODERATING REACTOR (LWGR)- a design unique to the USSR which figured in the CHERNOBYL incident. Some still in operation in Russian and Lithuania with 9 shut down.


Last one closed in 2010

3510/04/23

REACTOR TYPES – summary others• FBR - FAST BREEDER REACTOR - unlike all

previous reactors, this reactor 'breeds' PLUTONIUM from FERTILE 238U to operate, and in so doing extends resource base of URANIUM over 50 times. Mostly experimental at moment with FRANCE, W. GERMANY and UK, Russia and JAPAN having experimented with them.

• Other demonstration reactors

• SGHWR - STEAM GENERATING HEAVY WATER REACTOR - originally a British Design which is a hybrid between the CANDU and BWR reactors.

• HTGR - HIGH TEMPERATURE GRAPHITE REACTOR - an experimental reactor. The original HTR in the UK started decommissioning in 1975. The new Pebble Bed Modulating Reactor (PBMR) is a development of this and promoted as a 3+ Generation Reactor by South Africa.


3610/04/23

• FUEL TYPE - unenriched URANIUM METAL clad in Magnesium alloy

• MODERATOR - GRAPHITE

• COOLANT - CARBON DIOXIDE

• DIRECT RANKINE CYCLE - no superheat or reheat efficiency ~

20% to 28%.

ADVANTAGES:-• LOW POWER DENSITY - 1 MW/m3.

Thus very slow rise in temperature in fault conditions.

• UNENRICHED FUEL • GASEOUS COOLANT• ON LOAD REFUELLING• MINIMAL CONTAMINATION

FROM BURST FUEL CANS • VERTICAL CONTROL RODS - fall

by gravity in case of emergency.

MAGNOX REACTORS (also known as GCR):

DISADVANTAGES:-• CANNOT LOAD FOLLOW – [Xe

poisoning]

• OPERATING TEMPERATURE LIMITED TO ABOUT 250oC - 360oC limiting CARNOT EFFICIENCY to ~40 - 50%, and practical efficiency to ~ 28-30%.

• LOW BURN-UP - (about 400 TJ per tonne)

• EXTERNAL BOILERS ON EARLY DESIGNS.

3710/04/23

• FUEL TYPE - enriched URANIUM OXIDE - 2.3% clad in stainless steel


• COOLANT - CARBON DIOXIDE

• SUPERHEATED RANKINE CYCLE

(with reheat) - efficiency 39 - 41%

ADVANTAGES:-• MODEST POWER DENSITY - 5 MW/m3.

slow rise in temperature in fault conditions.• GASEOUS COOLANT (40- 45 BAR cf 160

bar for PWR)• ON LOAD REFUELLING under part load• MINIMAL CONTAMINATION FROM

BURST FUEL CANS

• RELATIVELY HIGH THERMODYNAMIC EFFICIENCY 40%

• VERTICAL CONTROL RODS - fall by gravity in case of emergency.

ADVANCED GAS COOLED REACTORS (AGR):

DISADVANTAGES:-• MODERATE LOAD FOLLOWING

CHARACTERISTICS

• SOME FUEL ENRICHMENT NEEDED. - 2.3%

OTHER FACTORS:-• MODERATE FUEL BURN-UP - ~

1800TJ/tonne (c.f. 400TJ/tonne for MAGNOX, 2900TJ/tonne for PWR).

• SINGLE PRESSURE VESSEL with pres-stressed concrete walls 6m thick. Pre-stressing tendons can be replaced if necessary.

3810/04/23

• FUEL TYPE - unenriched URANIUM OXIDE clad in Zircaloy

• MODERATOR - HEAVY WATER COOLANT - HEAVY WATER

ADVANTAGES:-• MODEST POWER DENSITY - 11 MW/m3.

• HEAVY WATER COOLANT - low neutron absorber hence no need for enrichment.

• ON LOAD REFUELLING - and very efficient indeed permits high load factors.

• MINIMAL CONTAMINATION from burst fuel can - defective units can be removed without shutting down reactor.

• MODULAR: - can be made to almost any size

CANDU REACTOR (PHWR):

DISADVANTAGES:-• POOR LOAD FOLLOWING

CHARACTERISTICS• CONTROL RODS ARE

HORIZONTAL, and therefore cannot operate by gravity in fault conditions.

• MAXIMUM EFFICIENCY about 28%OTHER FACTORS:-• MODERATE FUEL BURN-UP - ~

MODEST FUEL BURN-UP - about 1000TJ/tonne

• FACILITIES PROVIDED TO DUMP HEAVY WATER MODERATOR from reactor in fault conditions

• MULTIPLE PRESSURE TUBES instead of one pressure vessel.

3910/04/23

• FUEL TYPE - 3 – 4% enriched URANIUM OXIDE clad in Zircaloy

• MODERATOR - WATER

• COOLANT - WATER

ADVANTAGES:-• GOOD LOAD FOLLOWING

CHARACTERISTICS - claimed for SIZEWELL B. - most PWRs are NOT operated as such.

• HIGH FUEL BURN-UP- about 2900TJ/tonne –

• VERTICAL CONTROL RODS - drop by gravity in fault conditions.

PRESSURISED WATER REACTORS – PWR (WWER):

DISADVANTAGES:-• ORDINARY WATER as COOLANT -

pressure to prevent boiling (160 bar). If break occurs then water will flash to steam and cooling will be less effective.

• ON LOAD REFUELLING NOT POSSIBLE - reactor must be shut down.

• SIGNIFICANT CONTAMINATION OF COOLANT CAN ARISE FROM BURST FUEL CANS - as defective units cannot be removed without shutting down reactor.

• FUEL ENRICHMENT NEEDED. - 3-4%.

• MAXIMUM EFFICIENCY ~ 31 - 32%

latest designs ~ 35+%

OTHER FACTORS:-• LOSS OF COOLANT also means LOSS

OF MODERATOR so reaction ceases - but residual decay heat can be large.

• HIGH POWER DENSITY - 100 MW/m3, and compact. Temperature can rise rapidly in fault conditions. NEEDS active ECCS.

• SINGLE STEEL PRESSURE VESSEL 200 mm thick.

Boiling Water Reactor (BWR) is a derivative of PWR where water is allowed

to boil. Second most common reactor

4010/04/23

• FUEL TYPE - 2% enriched URANIUM OXIDE clad in Zircaloy


• COOLANT - WATER

ADVANTAGES:-• ON LOAD REFUELLING• VERTICAL CONTROL RODS which

can drop by GRAVITY in fault conditions.

NO THEY CANNOT!!!!

RMBK (LWGR): (involved in Chernobyl incident)

DISADVANTAGES:-• ORDINARY WATER as COOLANT -

flashes to steam in fault conditions hindering cooling.

• POSITIVE VOID COEFFICIENT !!! - positive feed back possible in some fault conditions -other reactors have negative voids coefficient in all conditions.

• IF COOLANT IS LOST moderator will keep reaction going.

• FUEL ENRICHMENT NEEDED. - 2%

• PRIMARY COOLANT passed directly to turbines. This coolant can be slightly radioactive.

• MAXIMUM EFFICIENCY ~30% ??

OTHER FACTORS:-• MODERATE FUEL BURN-UP - ~

MODEST FUEL BURN-UP - about 1800TJ/tonne

• LOAD FOLLOWING CHARACTERISTICS UNKNOWN

• POWER DENSITY probably MODERATE?

• MULTIPLE PRESSURE TUBES

4110/04/23

• FUEL TYPE - depleted Uranium or UO2 surround PU in centre of core. All elements clad in stainless steel.

• MODERATOR - NONE• COOLANT - LIQUID METAL

ADVANTAGES:-• LIQUID METAL COOLANT - at

ATMOSPHERIC PRESSURE. Will even cool by natural convection in event of pump failure.

• BREEDS FISSILE MATERIAL from non-fissile 238U – increases resource base 50+ times.

• HIGH EFFICIENCY (~ 40%) • VERTICAL CONTROL RODS drop by

GRAVITY in fault conditions.

FAST BREEDER REACTORS (FBR or LMFBR)

DISADVANTAGES:-• DEPLETED URANIUM FUEL

ELEMENTS MUST BE REPROCESSED to recover PLUTONIUM and sustain the breeding of more plutonium for future use.

• CURRENT DESIGNS have SECONDARY SODIUM CIRCUIT

• WATER/SODIM HEAT EXCHANGER. If water and sodium mix a significant CHEMICAL explosion may occur which might cause damage to reactor itself.

OTHER FACTORS:-• VERY HIGH POWER DENSITY - 600

MW/m3 but rise in temperature in fault conditions limited by natural circulation of sodium.

• Bradwell• Sellafield

• Hartlepool • Heysham• Hinkley Point (2 stations)

• Oldbury

• Sizewell (2 Stations)

• Wylfa

42

Potential Sites for New Nuclear Plant.

Three Sites:Dungeness, Braystones, Kirksanton were rejected by Government in October 2010

4310/04/23

• Schematic of Reactor is very similar to later PWRs (SIZEWELL) with 4 Steam Generator Loops.

• Main differences? from earlier designs. – Output power ~1600 MW from a single turbine

(cf 2 turbines for 1188 MW at Sizewell). – Each of the safety chains is housed in a separate building.

GENERATION 3 REACTORS: the EPR1300

Construction is under way at Olkiluoto, Finland, Flammanville, France and 2 in China.

Likely contender for new UK generation as British Energy is now owned by EDF

• Efficiency claimed at 37%• But no actual experience

and likely to be less

4410/04/23

GENERATION 3 REACTORS: the AP1000 • A development from SIZEWELL

• Power Rating comparable with SIZEWELL• Will two turbines be used ??• Two loops (cf 4 for EPR)• Designed for Passive Core

Cooling – e.g. water tank at top etc. Natural cooling by convection in fault conditions

• Significant reduction in components e.g. pumps etc.

Possible Contender for new UK reactors

See Website informatio0n on Nuclear Power for details of enhanced safety features.

4510/04/23

GENERATION 3 REACTORS: the ACR1000 • Development from CANDU 6 with similarities with the basic design concept

of the SGHWR originally developed in UK.

• Added Safety Features: Less Deuterium needed; vertical control rods; passive cooling as with AP1000.

See Video Clip of on-line refuelling

4610/04/23

ESBWR: Economically Simple BWR • A derivative of Boiling Water Reactor for which it is claimed has several safety features but which inherently has two disadvantages of basic design

•Vertical control rods which must be driven upwards

•Steam in turbines can become radioactive

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• Pebble Bed Modulating Reactors are a development from Gas Cooled Reactors.

• Sand sized pellets of Uranium each coated in layers of graphite/silicon carbide and aggregated into pebbles 60 mm in diameter.

• Coolant: Helium

• Connected directly to closed circuit gas turbine

• Efficiency ~ 39 – 40%, but possibility of CCGT??

• Graphite/silicon carbide effective cladding – thus very durable to high temperatures

GENERATION 3+ REACTORS: the PBMR

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GENERATION 3+ REACTORS: the PBMR • Unlike other Reactors, the PBMR uses a closed circuit high temperature

gas turbine operating on the Brayston Cycle for Power. This cycle is similar to that in a JET engine or the gas turbine section of a CCGT.

• Normal cycles exhaust spent gas to atmosphere.

• In this version the helium is in a closed circuit.

Fuel In

Air In

Combustion Chamber

Exhaust

CompressorTurbine

Generator

PBM Reactor

Heat Exchanger

Open Brayston Cycle

Closed Brayston Cycle

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• Efficiency of around 38 – 40%, but possibility of CCGT???

• Helium passes directly from reactor to turbine

• Pebbles are continuously fed into reactor and collected.

• Tested for burn up and recycled as appropriate ~ typically 6 times

GENERATION 3+ REACTORS: the PBMR

Documents

1 24/04/2014 ENV-2A82/ENV-2A82K Low Carbon Energy 2010 - 11 NUCLEAR POWER