Copyright © 2012 SCKCEN 3 rd LEADER International workshop Pisa & Bologna, 4-7 September 2012...

Copyright © 2012 SCK•CEN1

3rd LEADER International workshopPisa & Bologna, 4-7 September 2012

Didier De Bruyn (SCK•CEN)

Different ADS concepts in the world: EFIT, MYRRHA & the

others

Copyright © 2012 SCK•CEN

Contents

Nuclear energy in EuropeDealing with radioactive wasteSome ADS concepts from the past, within and outside

EuropeSome more recent concepts next presentationConclusion

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Nuclear energy in Europe

152 reactors in 15 countries in EU-27, producing 31% of EU’s electricity

The largest source of low carbon energy

Excellent safety recordEurope, a world leader –

but competition is building (Russia, Japan, USA, China, India)

Energy consumption shares in EU-25 (2005)

Electricity generation shares in EU-25 (2005)

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Nuclear fission in Europe’s low carbon energy policy

Nuclear fission contributes today 31% of EU electricity – the largest low carbon energy source

Target 2020 : Maintain competitiveness in fission technology and provide long term waste management solutions

For the longer term, we need to act now to:Complete the demonstration of Gen IV with closed fuel

cycle for increasing sustainability,Enlarge the nuclear fission applications beyond electricity

production, namely towards H2, heat, H20 desalination.

Ambitious R&D and Demo programmes need to start now to meet the required breakthroughs

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wasteminimisation

better use ofresources

reducedproliferation

risks

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Contents



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Fission generates High-Level Nuclear Waste

U235

nPu Np Am Cm

Actinides Minor Actinides

Neutron

Uranium Fission

Fuel

U238

n

n

n

U235

U238

Plutonium Neptunium Americium Curium

Minor Actinides

high radiotoxicity long lived wastethat are difficult to store due to:

Long lived (>1,000 years)

Highly radiotoxic

Heat emitting


spent fuel reprocessing

no reprocessing

Uraniumnaturel

Time (years)

Rel

ati

ve

rad

ioto

xici

ty

transmutationof spent fuel

Duration Reduction 1.000x

Volume Reduction 100x

Rad waste reduction is the motivation for Transmutation


GEN-IVFR

Losses Losses

Pu+MA

Pu+MA

Multirecycling

Repository

UOXPWR

Fuel fabrication

Reprocessing

CR = Conversion ratio = fissile material produced/fissile material destroyed.CR< 1 : burner ; CR>1 : breeder

From M. Salvatores et al. (GLOBAL 2009)

A first option : the FR introduction

Multiple recycle of TRU is feasible in a Fast Reactor (FR), whatever its coolant and fuel type: oxide, metal, carbide or nitride

2-5% MA in the fuel: close to standard fuel, if homogeneous recycle chosen and CR>0.8

Some impact on the fuel cycle, e.g. at fuel fabrication, due to the Cm-244 spontaneous fission neutron emission

Reprocessing needed to recover not-separated TRU (enhanced proliferation resistance)


multirecycling

multirecycling

Repository

UOXPWR

MOXPWR

Dedicated transmuter system

PuMA+Pu

Pu

Lo

sses

Lo

sses

MA

+P

u

MA

Fuel fabrication

ReprocessingLo

sses

The second option : the ADS scenario

Called "Double strata" Still considering Pu as a

resource Gen-IV FR deployment delayed Pu inventory can be stabilized MA management in dedicated

transmuter systems: e.g. ADS or critical FR with low CR.

Fuel: New fuel (with high MA content) needs to be developed

Reprocessing: to be developed in particular for U-free fuels. Choice of support matrix in fuel is relevant.

Potential impact on the fuel cycle (high decay heat, high neutron emissions)

From M. Salvatores et al. (GLOBAL 2009)


ADS: Accelerator Driven System for transmutation

Both critical reactors and sub-critical Accelerator Driven Systems are potential candidates as dedicated transmutation systems.

Critical reactors, however, loaded with fuel containing large amounts of MA pose safety problems caused by unfavorable reactivity coefficients and small delayed neutron fraction.

ADS operates flexible and safe at high transmutation rate

Proton Beam

Spallation Target

accelerator


Contents

Nuclear energy in EuropeDealing with radioactive wasteSome ADS concepts from the past, within and

outside EuropeSome more recent concepts next presentationConclusion

12


ADS in Europe: past and present

Energy Amplifier (EA) developed at CERN in the 90’s: devoted to a better use of resources; EA evolved then to XADS

ADONIS project in Belgium (1995-1996): solely devoted to the production of radio-isotopes for the medical industry; ADONIS evolved to MYRRHA in 1997; this project still exists

Both projects (XADS, MYRRHA) have been brought together in FP5 project PDS-XADS FP6 IP-EUROTRANS, finally FP7 CDTPDS-XADS (2002-2004): 80 MWth LBE-cooled and gas-

cooled, 50 MWth small-scaleEUROTRANS (2005-2010): two designs

MYRRHA, 70 MWth small-scale short-term, EFIT, 400 MWth mid-scale long-term

CDT (2009-2012): MYRRHA/FASTEF, 70-100 MWth short-term, sub-critical & critical

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The EFIT concept

Within the EUROTRANS project, the EFIT concept is developed for the transmutation of MAs

EFIT stays for European Feasibility for Industrial Transmutation

Its main features:ADS with keff (t) ≤ 0,97Lead-cooled sub-critical core (Tin=400 °C, Tout=480°C)MA & Pu Oxide fuel in inert matrix (MgO)several hundreds MW power

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1 Reactor Core 2 Active Zone3 Diagrid4 Primary Pump5 Cylindrical Inner Vessel6 Reactor Vessel7 Reactor Cavity8 Reactor Roof9 Reactor Vessel Support

10 Rotating Plug12 Above Core Structure13 Target Unit14 Steam Generator Unit15 Fuel Handling Machine16 Filter Unit17 Core Instrumentation18 Rotor Lift Machine19 DHR Dip Cooler

EFIT Reactor Assembly

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EFIT main process parameters

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Reactor Thermal Power, max design capability

416 MW

Proton beam power, max (800 MeV, 20 mA) 16 MW

Core Thermal Power 395 MW

Primary coolant flow rate, total 36,000 kg/s

Core inlet temperature 400 °C

Core outlet temperature, mean 480 °C

Feed water mass flow rate 250 kg/s

Feed water Inlet Temperature 335 °C

Steam Temperature 450 °C

Steam Pressure 14 MPa


Main dataProton Beam Energy, MeV 800

Max proton beam current, mA 20

Proton beam energy deposited, MW 11.2

Primary Pb Coolant inlet Temp. (°C) 400

Primary Pb Coolant outlet Temp. (°C) 450

Primary Pb d Coolant Flow-rate (kg/s) 1500

Target Pb Coolant Cold Temp. (°C) 419

Target Pb Coolant Hot Temp. (°C) 515

Target Pb Coolant Flow-rate (kg/s) 800

FA positions occupied 19

Outside diameter 78.2 cm

EFIT Windowless Spallation Target Concept

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252 position for Dummy Assemblies and Absorber Elements

42 FA

66 FA

72 FA

19 position for Target

Inner, Intermediate, Outer FA Design and Core Section

Enrichment = Pu/(Pu+MA) = 45.7%

EFIT Core Configuration

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Contents

Nuclear energy in EuropeDealing with radioactive wasteSome ADS concepts from the past, within and

outside EuropeSome more recent concepts next presentationConclusion

19


ADS outside Europe: past and present

Japan (JAEA):Experimental scale

30 MWth, then 60 MWthCooled by LBE (backup option being sodium)Keff ~ 0,93

Industrial scale800 MWth (see later)

Korea (KAERI)HYPER (Hybrid Power Extraction Reactor) designed since

1997Designed to transmute TC-99 and I-129 coming from PWRs1000 MWth; LBE-cooledKeff ~ 0,98

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Conceptual Design Study of the JAEA Reference ADS

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The JAEA design study has been concentrated on the concept of a “commercial-size” one with a thermal power of 800 MWth.

A superconducting linear accelerator is adopted to deliver a 1,5 GeV * 20 mA = 30 MW (maximum value) proton beam.

Lead-bismuth eutectic (LBE) is used as core coolant and spallation target.

Spallation target and accelerator are separated by a beam duct and a beam window inserted down to the active core.

Dedicated nitride fuel (MA, Pu)N + ZrN, where nitrogen is enriched up to 99 % with 15N, is a primary candidate, which can be recycled by a pyrochemical process with recovering 15N.

Concept of JAEA’s 800MWth ADS

Main pump

Beam window

Fuel region

Beam duct

Steamgenerator

Proton beam

Pb-Bi

Core support


JAEA Design Study : ADS Plant System

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Core barrel

Primary pump

Beam ductInner barrel

Steam generator

Guard vessel

Core support

Beam Window

Reactor vessel

Core barrel

Primary pump

Beam ductInner barrelInner barrel

Steam generator

Guard vessel

Core support

Beam Window

Reactor vessel


JAEA Design Study : Seismic Design

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58.3

2320.4

14.9

49

829.511.5

Crane

Fuel exchangerAir conditioning machine room

Control room

Electric machine room

ventilating machine room

Waste process room

Magnet trolley

Bending magnet

Primary pump

Steam generatorAuxiliary facility room

Reactor vessel

3-dimensional Seismic Isolation Device

58.3

2320.4

14.9

49

829.511.5

Crane

Fuel exchangerAir conditioning machine room

Control room

Electric machine room

ventilating machine room

Waste process room

Magnet trolley

Bending magnet

Primary pump

Steam generatorAuxiliary facility room

Reactor vessel

3-dimensional Seismic Isolation Device

Three-dimensional entire building seismic isolation system

3D seismic isolation devices support the entire reactor building.

The 3D isolator, absorbs vertical vibration by the air spring, while the horizontal one is absorbed primarily by the laminated rubber bearing.


JAEA Design Study : Beam Window

Expected window life : 2 years

Shape & thickness determined byThermal stressesStructural stresses (LBE

outside pressure)Material : T91 Irradiation damage taken into

accountAs well as corrosion rate

24Fue

l reg

ion

Fue

l reg

ion

Shi

eld

Shi

eld

Pb-Bi

Proton beam

Vacuum


Comparison JAEA – EFIT designs

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JAEA EFIT

Plant Proton energy 1.5 GeV x 20 mA 800 MeV x 20 mASpallation target concept LBE, Centered, window, cooled with primary coolant Pb, Centered, windowless, cooled with

independent Pb coolant loop

Maximum keff 0.97 0.97

Power (MWth) 800 384

Thermal efficiency 32% 40%

Fuel amount (HMt) 4.17 5.4

Transmutation performance 43.4kg/TWhth 45kg/TWhthReactivity swing compensation Proton current Proton current

Seismic design Three-dimensional anti-seismic supports Horizontal anti-seismic supports

Coolant Primary coolant LBE Pure LeadPrimary system temperature range (C) inlet: 300, outlet: 407 inlet: 400, outlet: 480

Coolant velocity (m/s) 2 2

Secondary coolant Low pressure boiling water Superheated water cycle

AssemblyMaximum Power density (W/cm3) 449 243

Linear power density 244 W/cm (average) <200W/cm(Cer-Cer)

Fuel assembly type Wrapperless Wrapper

Fuel Fuel (Pu,MA)N+ZrN (Pu, AM)O2+MgO(or Mo)

Practical density 90% 90%(CERCER),93%(CERMET)

Average burn-up 115 GWd/t 78GWd/t

Clad Cladding material 9Cr-1Mo T91Maximum cladding temperature 580 550


Contents



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Conclusion

Advanced nuclear fuel cycles are required to meet now the objective of making nuclear fission sustainable

The objectives of sustainability: waste minimisation, better use of the natural resources and reduced proliferation risks can be met with both fast reactors and dedicated burners (ADS)

Design studies have been performed within and outside Europe

Demonstrations (prototypes) should be planned and realized, to go from paper work to real work

Through the new MYRRHA research infrastructure (see next presentation), Belgium is contributing to this international endeavour.

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Copyright © 2012 - SCKCEN

PLEASE NOTE! This presentation contains preliminary data for dedicated use ONLY and may not be cited without the explicit permission of the author.

If this has been obtained, please reference it as a “personal communication. Copyright SCK•CEN”.

SCK•CENStudiecentrum voor Kernenergie

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Copyright © 2012 SCKCEN 3 rd LEADER International workshop Pisa & Bologna, 4-7 September 2012...

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