PEACE : a Prototype of the Energy Amplifier for a Clean Environment

Y. Kadi CERN, Switzerland

31 August 2006, Kjeller, Norway Future of ADS Y. Kadi 1 OUTLINE

PEACE: an Industrial Prototype of the Energy Amplifier for a Clean Environment

• Motivations • General Features of Energy Amplifier Systems • Experimental Validation • Implementation Strategy • Time Schedule

Future of ADS Y. Kadi 2 A new primary energy source

By 2050, the world’s consumption (+ 2%/y) should reach 34 TW, of which 20 TW should come from new energy sources: ⇒ A major innovation is needed in order to replace the expected “decay” of the traditional energy sources!

This implies a strong R&D effort, which is the only hope to solve the energy problem on the long term. This R&D should not exclude any direction a priori! Renewables Nuclear (fission and fusion) Use of hydrogen

Can nuclear energy play a major role?

Nuclear energy has the potential to satisfy the demand for a long time (at least 15 centuries for fission, essentially infinite for fusion if it ever works), and is obviously appealing from the point of view of atmospheric emissions.

Future of ADS Y. Kadi 3 World nuclear electricity production by scenarios (INPRO Phase-IA Report)

800

700

F_upgrading 600 Desalination Schematic illustration of the four Add Heat SRES storyline500 families Add H2 (Source:IPCC) 400 Add Elec Exajoule Heat 300 Hydrogen Electricity 200

100

0 Potential global market for nuclear electricity, hydrogen, heat and desalination 2000 2010 2020 2030 2040 2050 2060for the 2070 A1T Scenario 2080 2090assuming 2100 aggressive nuclear cost improvements Future of ADS Y. Kadi 4 Which type of nuclear energy?

Nuclear fusion energy: not yet proven to be practical. Conceptual level not reached (magnetic or inertial confinement?). ITER a step, hopefully in the right direction. Nuclear fission energy: well understood, and the technology exists, with a long (≥ 50 years) experience, however, present scheme has its own problems: • Military proliferation (production and extraction of plutonium); • Possibility of accidents (Chernobyl [1986]; Three Mile island [1979]); • Waste management. However, it is not given by Nature, that the way we use nuclear fission energy today is the only and best way to do it. One should rather ask the question: Could nuclear fission be exploited in a way that is acceptable to Society? To answer this question, Carlo Rubbia and his team at CERN have carried out, in the 1990’s, an extensive experimental programme (FEAT, TARC) which has led to a conceptual design of a new type of nuclear fission system, driven by a proton accelerator, with very attractive properties (Pioneering work by Ernest Lawrence, Wilfrid Bennett Lewis, Hiroshi Takahashi, Charles D. Bowman).

Future of ADS Y. Kadi 5 Basic Principle of Energy Amplifier Systems

One way to obtain intense neutron sources is to use a hybrid sub-critical reactor-accelerator system called Accelerator- Driven System:

The accelerator bombards a target with high-energy protons which produces a very intense neutron source through the spallation process.

These neutrons can consequently be multiplied (fission and n,xn) in the subcritical core which surrounds the spallation target.

Future of ADS Y. Kadi 6 OUTLINE

PEACE: an Industrial Prototype of the Energy Amplifier for a Clean Environment

• Motivations • General Features of Energy Amplifier Systems • Experimental Validation • Implementation Strategy • Time Schedule

Future of ADS Y. Kadi 7 General Features of Energy Amplifier Systems

air inlet

Subcritical system driven by a proton air

RVACS flow paths outlet

accelerator: Fast neutrons (to fission all stack transuranic elements) grade Fuel cycle based on thorium containment dome Beam Secondary coolant (minimisation of nuclear waste) Normal lead level Overflow path Lead as target to produce neutrons through spallation, as neutron moderator and as heat Seismic isolator EBDV carrier Heat exchanger Main vessel

Deterministic safety with Contaiment vessel passive safety elements (protection Hot rising liquid Hot rising liquid against core melt down and beam Hot air riser Cold, descending liquid Cold, descending liquid

window failure) Beam pipe Cold air downcomer Thermal insulating wall

Main silo Plenum region

Core Core

Fuel region

Spallation region

Future of ADS Y. Kadi 8 General Features of Energy Amplifier Systems

Proton Beam

Beam channel Collimator

Extended lead molten medium Liquid Lead Fuel

Breeding 232 → 233 Beam n ( Th U) window

n n n n Spallation Fission 233 → ( U Fission Fragments)

Future of ADS Y. Kadi 9 The Spallation Process (1)

Several nuclear reactions are capable of producing neutrons × However the use of protons minimises the energetic cost of the neutrons produced

Deposited Incident Particle Beam Neutron Target Neutrons Nuclear Energy & Currents Yields Power Emmitted Reactions Per Neutron Typical Energies (part./s) (n/inc.part.) (MW) (n/s) (MeV)

(e,γ) & (γ,n) e- (60 MeV) 5 × 1015 0.04 0.045 1500 2 × 1014

H2(tn)He4 H3 (0.3 MeV) 6 × 1019 10-4 — 10-5 0.3 104 1015

Fission - 1 57 200 2 × 1018

Spallation 14 0.09 30 2 × 1016 (non-fissile target) p (800 MeV) 1015

Spallation 16 (fissionable target) 30 0.4 55 4 × 10

Future of ADS Y. Kadi 10 The Spallation Process (2)

There is no precise definition of spallation Ç this term covers the interaction of high energy hadrons or light nuclei (from a few tens of MeV to a few GeV) with nuclear targets.

××ItIt corresponds corresponds to to the the reaction reaction mechanismmechanism by by which which this this high high energyenergy projectile projectile pulls pulls out out of of the the targettarget some some nucleons nucleons and/or and/or light light particles,particles, leaving leaving a a residual residual nucleus nucleus (spallation(spallation product) product)

××DependingDepending upon upon the the conditions, conditions, thethe number number of of emitted emitted light light particles,particles, and and especially especially neutrons, neutrons, maymay be be quite quite large large

××ThisThis is is of of course course the the feature feature of of outermostoutermost importance importance for for the the so- so- calledcalled ADS ADS

Future of ADS Y. Kadi 11 The Spallation Process (3)

At these energies it is no longer correct to think of the nuclear reaction as proceeding through the formation of a compound nucleus.

FastFast Direct Direct Process: Process: ××Intra-NuclearIntra-Nuclear Cascade Cascade (nucleon-nucleon(nucleon-nucleon collisions) collisions)

Pre-CompoundPre-Compound Stage: Stage: ××Pre-EquilibriumPre-Equilibrium ××Multi-FragmentationMulti-Fragmentation ××FermiFermi Breakup Breakup

CompoundCompound Nuclei: Nuclei: ××EvaporationEvaporation (mostly (mostly neutrons) neutrons) ××High-EnergyHigh-Energy Fissions Fissions

Inter-NuclearInter-Nuclear Cascade Cascade

Low-EnergyLow-Energy Inelastic Inelastic Reactions Reactions ××(n,xn)(n,xn) ××(n,nf)(n,nf) ××etc...etc...

Future of ADS Y. Kadi 12 The Spallation Process (4)

The relevant aspects of the spallation process are characterised by:

Spallation Neutron Yield (i.e. multiplicity of emitted neutrons) Î determines the requirement in terms of the accelerator power (current and energy of incident proton beam).

Spallation Neutron Spectrum (i.e. energy distribution of emitted neutrons) Î determines the damage and activation of the structural materials (design/lifetime of the beam window and spallation target, radioprotection) Spallation Product Distributions Î determines the radiotoxicity of the residues (waste management). Energy Deposition Î determines the thermal-hydraulic requirements (cooling capabilities and nature of the spallation target).

Future of ADS Y. Kadi 13 Spallation Neutron Spectrum

The spectrum of spallation neutrons evaporated from an excited heavy nucleus bombarded by high energy particles is similar to the fission neutron spectrum but shifts a little to higher energy Õ ≈ 3 – 4 MeV.

1E+0 Fission Source Spallation Source 1E-1

1E-2

1E-3

1E-4

Neutron Source Spectrum (arbitrary units) 1E-5

1E-6 1E+2 1E+3 1E+4 1E+5 1E+6 1E+7 1E+8 Energy (eV)

Future of ADS Y. Kadi 14 Spallation Product Distribution

The spallation product distribution varies as a function of the target material and incident proton energy. It has a very characteristic shape: Õ At high masses it is characterized by the presence of two peaks corresponding to (i) the initial target nuclei and (ii) those obtained after evaporation Õ Three very narrow peaks corresponding to the evaporation of light nuclei such as (deuterons, tritons, 3He and α) Õ An intermediate zone corresponding to nuclei produced by high-energy fissions

Future of ADS Y. Kadi 15 Energy Amplifiers vs Critical Reactors Main objective is to reduce the production of nuclear waste (TRU)

Energy Amplifier : sub-critical fast neutrons Thorium + 233U +TRU (Pu + Minor Actinides)

Reactor : critical slow neutrons Uranium + Pu

Future of ADS Y. Kadi 16 Physics of Sub-Critical Systems

EAsEAs operate operate in in a a non non self-sustained self-sustained chainchain reaction reaction mode mode × minimises criticality Chain Reaction Nuclear Cascade × minimises criticality andand power power excursions excursions High Energy n Proton EAsEAs are are operated operated in in a a sub-critical sub-critical mode mode (1 GeV) × stays sub-critical whether Energy × stays sub-critical whether Critical accelerator is on or off Losses n Capture n Reactor Amplifier accelerator is on or off nn × extra level of safety against Fission (200 MeV/fission Fission × extra level of safety against ~ 2.5 n/fission) criticality accidents n criticality accidents (200 MeV/fission The accelerator provides a control ~ 2.5 n/fission) The accelerator provides a control Fission mechanism for sub-critical systems n mechanism for sub-critical systems Losses Capture × more convenient than Effective neutron multiplication factor Fission × more convenient than controlcontrol rods rods in in critical critical reactor reactor Production k= ××safetysafety concerns, concerns, neutron neutron Absorption + Losses Externally driven process: economyeconomy Self-sustained process: k < 1 (k = 0.98) k = 1 E = G × E EAs provide a decoupling of the neutron tot p EAs provide a decoupling of the neutron (if k < 1 the Reactor stops source (spallation source) from the fissile if k > 1 the Reactor is supercritical) source (spallation source) from the fissile Energy Produced Beam Energy fuelfuel (fission (fission neutrons) neutrons) ⇒ The time derivative of the power ⇒ Constant Energy Gain kept equal to zero by control EAsEAs accept accept fuels fuels that that would would not not be be acceptableacceptable in in critical critical reactors reactors ××MinorMinor Actinides Actinides ××HighHigh Pu Pu content content ××LLFF...LLFF...

Future of ADS Y. Kadi 17 Safety margin from prompt criticality For a critical system, it is measured by the fraction of delayed neutrons. For the Energy Amplifier, it is an intrinsic property, and can be chosen. Subcriticality implies strong damping of reaction to reactivity insertion, making the system very stable (presence of higher modes in neutron flux).

Keff < ksource The parameters of the system can be chosen so that k < 1 at all times.

Future of ADS Y. Kadi 18 Reactivity Insertions

+2.5 $ criticality insertion Insertion time 15 mS 100 100 There is a spectacular difference between a critical reactor and an EA Critical (reactivity in $ = ρ/β; ρ = (k–1)/k) : Reactor Mode

Figure extracted from C. Rubbia et al., CERN/AT/95-53 9 (ET) showing the effect of a rapid reactivity insertion in the Energy Amplifier for two values of 10 10 subcriticality (0.98 and 0.96), compared with a Fast Breeder Critical Reactor. 2.5 $ (Δk/k ~ 6.5×10–3) of reactivity Peak power/Nominal power change corresponds to the sudden extraction of all control rods from the

reactor. Energy Amplifier Mode Keff=0.98

Keff=0.96 1 1 0 4 8 12 16 20 Time (ms) Figure 1.3 Future of ADS Y. Kadi 19 Subcriticality limit vs operating and accident conditions

Future of ADS Y. Kadi 20 Energy Amplifiers vs Critical Reactors Main objective is to reduce the production of nuclear waste (TRU)

Energy Amplifier : sub-critical fast neutrons Thorium + 233U +TRU (Pu + Minor Actinides)

Reactor : critical slow neutrons Uranium + Pu

Future of ADS Y. Kadi 21 Maximizing fission probability

The strategy consists in using the hardest possible neutron flux, so that all actinides can fission instead of accumulating as waste.

Future of ADS Y. Kadi 22 Fast neutrons and high burn-up

0.25

0.2 Thermal neutrons All fission

0.15

0.1 Fast neutrons Thermal neutrons All fission 0.05 Xe -135 only Fraction of All neutrons captured by FF

0 0 20 40 60 80 100 120 1400 160 Integrated Burn-up rate, Gwatt×day/t PWR AE

Future of ADS Y. Kadi 23 Energy Amplifiers vs Critical Reactors Main objective is to reduce the production of nuclear waste (TRU)

Energy Amplifier : sub-critical fast neutrons Thorium + 233U +TRU (Pu + Minor Actinides)

Reactor : critical slow neutrons Uranium + Pu

Future of ADS Y. Kadi 24 Thorium as fuel in a system breeding 233U

It is the presence of the accelerator which makes it possible to choose the optimum fuel. Low equilibrium concentration of TRU makes the system favourable for their elimination: Pu 10–4 in Th vs 12% in U. Future of ADS Y. Kadi 25 Energy Amplifier

Equilibrium concentrations are orders of magnitude lower than in a Uranium-plutonium based fuel Elément Limite asymptotique 8 1.0x10 232 ENERGY AMPLIFIER Th 7,637 E-1

[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[ 231 [[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[ Th-232 1 Pa 1,061 E-4 7 1.0x10 232U 1,306 E-4 233 [[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[ U-233 U 8,919 E-2 0.1 6 1.0x10 234U 3,368 E-2

U-234 235U 8,196 E-3 [[[[[[[[[[[[[[ [[[[[[[[[[[[[[[[[ 0.01 [[[[[[[[[[[[[ 5 [[[[[[[[[[[ Pa-233 236 [[[[[[[[[ U 8,395 E-3 1.0x10 [[[[[[[ [ [[[[[ Stockpile relative concentration [[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[[ [[ [[ [[ [[[[[[[ [ [[ [ [[ [ [ [[[[[[[[[[[[ [[[[[[[[[[[ [ [ [[ [[ [[ [[[[[ [ [ [[[[[ [[[ [[[[[ [[[[ [[[ [ [[ [[[[ [[[[[[[[ [ [ 238 [[ [[[[[[[[ U-235 U 1,440 E-5 [[ [[[[[[ [ [[[[ -3 [ [[[[[ 1x10 [ [[[[ [[[[[[ [ [[[ [[[[[[[[[[[ 237 [[[ [[[[[[[[[ Pa-231 Np 2,168 E-3 4 [[[ [[[[[[[[ 1.0x10 [ [[ [[[[[[ [[ [[[[[[ [ [[[[[[ U-236 Stockpile, grams [ [[[[ 238 [ [[[[[ U-232 Pu 1,958 E-3 [[ [[[[ [[[[[[[[[ [ [[[ [[[[[[[[[[[[[[[[[[[[[[ [ [[[[ [[[[[[[[[[[[[[[ [ [[[ [[[[[[[[[[[[ -4 [[[ [[[[[[[[ [[ 1x10 239 [ [[[[[[[ [[[[[[ [[[[[[ Pu 6,374 E-4 [ [[[[[[[[[[[[[[[[[ [[[[[[[ [[[[[[[[[[[ [[[[[ [[[[[[[[ [[[[[[[[[[ [[[[[ [[[[[[[[[ 1000 [ [[[[[[[[[[[[ [[[[[[[[[[[[[ [[[[[[[[[[ [[[[[[[[[ [[[[[ [[[ [[[[[[[[[[ Th-230 240 3,703 E-4 [[[[[ [[[ [[[[[[[[ [[[[ Pu [[[[ [[[ [[[[[ [[[ Np-237 [[[ [[[ [[[[[ [[[[[ [[[ [[[ [[[[ [[[ [[[ [[ [[[[ [[[[ -5 241 [[ [[[ [[[ [[[ 1x10 7,034 E-5 [[ [[ [[[[[[ [[ [[[[ Pu [ [[ [[[[[[ [[[ [[[[[[[[[[[[[[[[[[[[[[[[[[ [ [[ [[[[[[ [[ [[[[[[[[[[[ [[[[[[ Pu-238 -6 [ [[ [[[[[ [[ [[[[[[[[ [[[[ 100 [ [ [[[[[ [[ [[[[[ [[[[ 1x10 [ [[ [[[[[ [[ [[[[[[[[[ [[[[[[ 242 4,572 E-5 [ [ [[[[[ [[ [[[[[[ [[ Pu [[ [[ [[[ [[[[[[[[[[ [[[[[[[[ [[[[ [ [ [[[ [[[[[[[[[[[[[[[[[[[[[[[[[ [[[[ [ [[[ [[[[[[[[[[[[[[[[ [ [[ [[[ [[[[[[[ [[[[ [[[[ [ [ [ [[[[ [[[[[[[[ [[[[[ [[ [[[ 241 [ [[[ [[[[[[[ [[[ [[ [[[ Am 1,547 E-5 [ [[ [[[[ [[[[ [[ [ [[[ [[[[[[[ [[[[[ [ [[ [[[[[ [[[[ [[[ [[[ [[ [[[[[ [[[[ [[ [[ 10 [ [[[[[[[[ [ [[[[[[ [[ 243Am 1,372 E-5 0 10 20 30 40 50 60 70 80 90 100 110 120 130 Integrated Burn-Up, GW day/ton 244Cm 1,303 E-5

Future of ADS Y. Kadi 26 CAPRA Core (CEA)

Plutonium incineration in fast neutron reactors

140 Uranium-Plutonium Fast Breeder 980

120 840

100 700

80 560

60 420

40 280

20 140 Incineration Net Pu consumption/unit Energy, kg/TWhe Net Pu consumption/unit

0 0 Net Pu consumption/unit Energy, kg/GWe/year Breeding -20 -140 0 102030405060 Percentage Plutonium in Mixture

Future of ADS Y. Kadi 27 Radiotoxicity

The radiotoxicity of spent fuel reaches the level of coal ashes after only 500 years, and is similar to what is predicted for future hypothetical fusion systems

Future of ADS Y. Kadi 28 Accelerator choice

Cyclotron = Linear accelerator = MODULAR, realised on Solution for Research Centres industrial scale & highly centralised Cost effective ; applicable in production isolated regions ;applicable for desalination & cogeneration

Future of ADS Y. Kadi 29 MOTIVATION for ADS

Accessible, clean & cheap energy for countries requiring more energy to reach normal development.

Nuclear energy without accidents and radioactive waste. (sub-critical & fast neutrons)

Nuclear energy without proliferation risks (Th fuel)

Future of ADS Y. Kadi 30 OUTLINE

PEACE: an Industrial Prototype of the Energy Amplifier for a Clean Environment

• Motivations • General Features of Energy Amplifier Systems • Experimental Validation • Implementation Strategy • Time Schedule

Future of ADS Y. Kadi 31 The Three Levels of ADS Validation Three different levels of validation of an ADS can be specified:

First, validation of the different component concepts, taken separately (accelerator, target, subcritical core, dedicated fuels and fuel processing methods). In Europe: The FEAT, TARC, MUSE & YALINA experimental programs and the MEGAPIE project are significant examples. : IP-EUROTRANS

Second, validation of the coupling of the different components in a significant environment, e.g. in terms of power of the global installation, using as far as possible existing critical reactors, to be adapted to the objectives.

Third, validation in an installation explicitly designed for demonstration. This third step should evolve to a demonstration of transmutation fuels, after a first phase in which the subcritical core could be loaded with “standard” fuel.

Y. Kadi 32 Review of Sub-Critical Core Experiments

Highly specified experiments have been carried out to verify the fundamental physics principle of Energy Amplifier Systems:

TheThe First First Energy Energy Amplifier Amplifier Test Test (FEAT): (FEAT):S. S. Andriamonje Andriamonje et et al. al. PhysicsPhysics Letters Letters B B 348 348 (1995) (1995) 697–709 697–709 and and J. J. Calero Calero et et al. al. Nuclear Nuclear InstrumentsInstruments and and Met Methodshods A A 376 376 (1996) (1996) 89–103; 89–103;

TheThe MUSE MUSE Experiment Experiment (MUltiplication (MUltiplication de de Source Source Externe): Externe): M. M. SalvatoresSalvatores et et al., al., 2nd 2nd ADTT ADTT Conf., Conf., Kalmar, Kalmar, Sweden, Sweden, June June 1996; 1996;

TheThe YALINA YALINA Experiment Experiment (ISTC-B-70): (ISTC-B-70): S. S. Chigrinov Chigrinov et et al., al., InstituteInstitute of of Radiation Radiation Physics Physics & & Chemistry Chemistry Problems, Problems, National National AcademyAcademy of of Sciences, Sciences, Minsk, Minsk, Belarus. Belarus.

Future of ADS Y. Kadi 33 Physics Validation Sequence

CONFIGCONFIG SOURCE SOURCE KINETICS KINETICS POWER POWER EFFECTS EFFECTS FEATFEAT SPALL SPALL FAST FAST NONO MUSEMUSE DD/DT DD/DT FAST FAST NONO YALINAYALINA DD/DT DD/DT THERMAL THERMAL NONO YALINAYALINA DD/DT DD/DT FAST FAST NONO TRADETRADE SPALL SPALL THERMAL THERMAL YESYES PEACEPEACE SPALL SPALL FAST FAST YESYES

Future of ADS Y. Kadi 34 The FEAT (First Energy Amplifier Test) Experiment 1993-94

EXPERIMENTAL DETERMINATION OF THE ENERGY GENERATED BY NUCLEAR CASCADES FROM A PARTICLE BEAM

CEN, Bordeaux-Gradignan, France CIEMAT, Madrid, Spain CSNSM, Orsay, France CEDEX, Madrid, Spain CERN, Genève, Switzerland Dipartimento di Fisica e INFN, Università di Padova, Padova, Italy INFN, Sezione di Genova, Genova, Italy IPN, Orsay, France ISN, Grenoble, France Sincrotrone Trieste, Trieste, Italy Universidad Autónoma de Madrid, Madrid, Spain Universidad Politecnica de Madrid, Madrid, Spain University of Athena, Athens, Greece Université de Bâle, Bâle, Switzerland University of Thessalonic, Thessalonique, Greece

Future of ADS Y. Kadi 35 FEAT

Top and side view of the FEAT assembly, on the T7 beam line of the CERN-PS complex.

155 890 155

25.4

Stainless 251 steel flange 125 35 15.8 50.8 Stainless 155 Empty steel vessel space 600 Stainless Uranium steel flange bars BEAM BEAM 1524 127 1070

Water Water Aluminium tube

Uranium bars 635 313 BAR POSITIONS 165 270 BARS WITH URANIUM 203 10 EMPTY BARS 1219.2

Future of ADS Y. Kadi 36 The FEAT experiment

3.6 tons of natural uranium

Future of ADS Y. Kadi 37 Main FEAT results

Energy gain vs. kinetic energy (Average from all counters & MonteCarlo)

40 S. Andriamonje et al., Phys. Lett. B348 (1995) 697-709

25 G G = 0 ~ 30 20 (1 - k) Energy gain

G0 ~ 3 15 k ~ 0.9

Avg. Measured Gain Monte Carlo Gain

Proton Kinetic Energy (GeV) 0 0.5 1 1.5 2 2.5 3 3.5

Future of ADS Y. Kadi 38 Conclusions from FEAT

Consistant measurement of the energy gain.

Validation of innovative MC simulation tool.

Energy gain increases with particle beam energy Ç constant above 900 MeV Ç modest requirement for Energy Amplifier.

The first Energy Amplifier (with a power rating ≈ watt) was operated at CERN in 1994.

Future of ADS Y. Kadi 39 The MUSE Experiment

MASURCA facility (courtesy of CEA)

The Pulsed Neutron Source «GENEPI »

Future of ADS Y. Kadi 40 Main MUSE Results

MUSE 1 MUSE 2 MUSE 3 MUSE 4

12/95 09-12/96 01-04/98 11/99-08/04

Cf252 Cf252 (D,T) thermalised GENEPI

Stochastic Stochastic Pulsed Pulsed

Apparent worth Buffer : Na or Spectrum source Dynamic of the source SS Dynamic measurements Φ* Φ* measurements M.A. Fission rates Spectrum index Neutron (test) spectrometry Lead zone

Future of ADS Y. Kadi 41 The YALINA Experiment

General view of the YALINA fuel subassembly. Future of ADS Y. Kadi 42 Main YALINA Results

Neutron pulses measured by 3He-counters in different experimental channels.

–Close to criticality: straight line, α constant Layout of the Yalina core –Deep subcriticality: α time dependent

Future of ADS Y. Kadi 43 The TARC Experiment

¾ Understanding the phenomenology of spallation neutrons in lead (neutron flux measurements by electronic detectors and by activation measurements, etc.)

¾ Direct test of Transmutation of Long-Lived Fission Fragments 99 129 ( Tc, I) by Adiabatic Resonance Crossing

¾ Development & validation of appropriate simulation/computing tools

Future of ADS Y. Kadi 44 Transmutation of Nuclear Waste: Fission Products

Fission Fragments activity and toxicity after 1000 years of cool-down in a Secular Repository (Values are given for 1 GWe ´ year)

Radio- Half- Mass Activity Ingestive Dilution Isotope Life @ 1000 yr Toxicity Class A (kg) (years) (Ci) (Sv) × (m3) 103 129I 1.57 x 8.09 1.43 19.58 178.47 107 99Tc 2.11 x 16.61 284.29 27.67 947.65 105 126Sn 1.0 x 1.187 33.79 3.20 9.65 105 135Cs 2.3 x 34.12 39.32 9.87 39.32 106 93Zr 1.53 x 26.11 65.64 2.38 18.75 106 79Se 6.5 x 0.30 2.06 0.745 0.59 105 Future of ADS Y. Kadi 45 Principle of LLFP destruction

99 × 5 → 100 γ Tc (t1/2 = 2.1 10 ans) + n Tc (t1/2 = 15.8 s) + prompts (1) ARC maximizes 100 100 Neutron Capture Rate Ru*→ Ru (stable) + γ's (2) 174μs 92μs 104

103 neutron slowing down Thermal 102

101

100

10Ð1

Ð2 Cross-Section (barns) 10 Neutron Capture 10Ð3 Cross-Section of 99Tc 10Ð4 10Ð5 10Ð3 10Ð1 101 103 105 107 Neutron Energy (eV)

Future of ADS Y. Kadi 46 Adiabatic Resonance Crossing

Adiabatic Crossing of the 5.6 eV Resonance of 99Tc

10000

1000

Iso-lethargic steps ξ = 9.6×10Ð3

100 Cross-section (barns)

10 4 4.5 5 5.5 6 6.5 7 Neutron Energy (eV)

Future of ADS Y. Kadi 47 Experimental Setup

THE TARC EXPERIMENT

0 5 10 m

1.9 m Aluminium Foil System TARC LEAD MWPC #1

DVT02 MWPC #2 Vacuum pipe BHZ03 3.74 m Beam Embeco Transformer #2 2.09 m He bag Beam QDE04 QFD05 DVT01 Transformer #1 He bag 0.44 m

Concrete Floor 3.2 m

Beam Hodoscope (PM 1 & 2) Beam Hodoscope (PM 3 & 4) [slow extraction mode] [slow extraction mode]

Side view of the TARC experimental area showing the details of the beam line. In the slow extraction mode the two station beam hodoscope is introduced in the beam line where indicated.

Future of ADS Y. Kadi 48 Experimental Setup (2)

SimulationSimulation of of neutron neutronss produced produced by by a a single single 3.53.5 GeV/c GeV/c proton proton (147(147 neutrons neutrons produced, produced, 55035 55035 scattering) scattering)

Future of ADS Y. Kadi 49 TARC Results

-2 -1 2 3 4 5 6 7 10 10 1 10 10 10 10 10 10 10 10 8 10 10

a) 99Tc (216.1 mg) a) 10 7 10 9

3.57 GeV/c

10 6 10 8 protons 9 10 5

5 7 protons of 3.5 GeV/c) 10 10 protons of 2.5 GeV/c) 9 9 for 10 for 10 2.5 GeV/c

2 scale 2 10 4 10 6 129I (64.7 mg) scale 127 3 5 I (10.44 mg) 10 10

3He Scintillation 3 Number of Captures per 10

E×dF/dE (neutron/cm He Ionization E×dF/dE (neutron/cm 4 10 2 6Li/233U Detectors 10 4 10 Monte Carlo

3 10 1 10 -2 -1 2 3 4 5 6 7 10 10 1 10 10 10 10 10 10 10 -200 -150 -100 -50 0 50 100 150 200 Distance to the Centre of the Lead Volume (cm) Neutron Energy (eV) 1.4 0.10 eV b) b) 6 6 10 1.46 eV (In) 10 1.2

5 eV (Au)

18 eV (W) 1 10 5 10 5

100 eV 0.8 protons) 9 4 4 10 480 eV 10 /eV/10

2 1 keV

Data/MC 0.6

3 3 10 10 keV 10 dF/dE (n/cm 0.4 180 keV

2 2 10 10 99 129 127 3He Ionization 0.2 Tc (216.1 mg) I (64.7 mg) I (10.44 mg) Activation Foils 3He Scintillation 6LiF/233U Detectors Monte Carlo 0 -200 -150 -100 -50 0 50 100 150 200 -200 -150 -100 -50 0 50 100 150 200 Distance to the Center of Lead Volume (cm) Distance to the Centre of the Lead Volume (cm)

Future of ADS Y. Kadi 50 TARC Results (2)

103 Capture TARC Measured Cross Section Cross section Chou et al. Cross Section TARC Measured 99Tc Capture Rate 99Tc Capture Rate Simulation (JENDL-3.2)

Scale 102 106 protons 9 5 101 10 ./dE per 10 capt Scale 0 4 10 10 E×dN Apparent Cross Section (barn) Apparent Cross Section Transmutation Rate

3 101 10 1 10 100 1000 Neutron Energy (eV)

Future of ADS Y. Kadi 51 LLFP Incineration

1014 Neutron Spectra in the entire device 1013 Fuel

1012 Spallation Target 1011 Target Vessel

10 10 Primary Coolant

9 10 Reactor Vessel

108 Secondary Coolant Neutron Flux (arbitrary units)

107

106 Reactor Roof

105 10-3 10-2 10-1 100 101 102 103 104 105 106 107 108

Neutron Energy (eV)

Future of ADS Y. Kadi 52 LLFP Incineration (2)

Monte Carlo simulation of the neutron fluence in the lead outside the Energy Amplifier core after introduction of 2.7 mg/cm3 of 99Tc.

2.5x10-3 C. Rubbia, CERN/LHC/97-04 (EET)

2.0x10-3 20.3 eV

1.5x10-3 5.6 eV

1.0x10-3 Relative Flux dN/dlog(E)

5.0x10-4

Diffusive Re-fill 0.0x100 1x10-2 1x10-1 1x100 1x101 1x102 1x103 1x104 1x105 1x106 Neutron Energy(eV)

Future of ADS Y. Kadi 53 LLFP Incineration (3)

Elapsed time (years) 0 0.5 1 1.5 2 1.2 Tc-99 density: 2.686 mg/cm3 C. Rubbia Relative concentration to Pb: 260 ppm CERN/LHC/97-04 (EET) Volume = 0.409 m3 1.0

Ru-100 0.8 Tc-99

0.6

− x 82.1 [GWatt d /t] 0.4 1.11 e

Tc-99 Average concentration, arbitrary units 0.2

Ru-101 Ru-102 0.0 0 20 40 60 80 100 120 140 160 Burnup in the EA Core, GWatt day/ton

Future of ADS Y. Kadi 54 The Three Levels of ADS Validation Three different levels of validation of an ADS can be specified:

Y. Kadi 55 TRADE Project

The TRADE experiment suggested by C. Rubbia, first worked-out in an ENEA/CEA/CERN feasibility study and presently assessed by a wider international group (lead: ENEA, CEA, DOE, FZK), is a significant step towards the ADS demonstration, i.e. within the second phase of ADS validation

Coupling of a proton accelerator to a power TRIGA Reactor via a spallation target, inserted at the centre of the core.

Range of power : in the core : 200 - 1000 KW, in the target : 20 - 100 KW.

The main interest of TRADE, as compared to the MUSE experiments, is the ability of incorporating the power feedback effects into the dynamics measurements in ADS and to address ADS operational, safety and licensing issues.

Future of ADS Y. Kadi 56 The TRADE Facility - Reactor and Accelerator Buildings

Control Room Window

Cyclotron (section) Core Reactor Beam Pipe

Shielded Beam Pipe Tunnel

Future of ADS Y. Kadi 57 TRIGA MARK II REACTOR

Future of ADS Y. Kadi 58 TRIGA MARK II REACTOR

Future of ADS Y. Kadi 59 Overall Lay-out of the TRADE Facility

Top view with bending magnets

Core cross-section

Future of ADS Y. Kadi 60 The accelerator

Future of ADS Y. Kadi 61 Types of Experiments

The planned experiments would have allowed to validate different operational modes of a full power ADS: start-up and shut down procedures, operation and monitoring of the system at steady state, monitoring of the time evolution of the reactivity, and practical coupling of an accelerator, a spallation target and the subcritical core.

Most of these features are largely independent on the type of neutron spectrum in the core and on the type of proton accelerator.

Of course, no significant demonstration of waste transmutation in a fast neutron spectrum was foreseen.

Future of ADS Y. Kadi 62 The Three Levels of ADS Validation Three different levels of validation of an ADS can be specified:

Y. Kadi 63 The Prototype of the Energy Amplifier for a Clean Energy

The key objective of PEACE is threefold:

Demonstrating the technical feasibility of a fast neutron operated Accelerator Driven System (ADS); p Lead-Bismuth Eutectic coolant;

p Incineration of TRUs and LLFF while producing energy.

Future of ADS Y. Kadi 64 The PEACE : Plant Layout

Future of ADS Y. Kadi 65 The modified version of SVBR-75 reactor for PEACE

Steam generator

∅ 3 500

Future of ADS Y. Kadi 66 The PEACE : Global Parameters

a pa a ete s o t e e e e ce co gu at o

Global Parameters Symbol EADF EADF Units Initial fuel mixture MOX (U-Pu)O2 (Th-Pu)O2 Initial fuel mass mfuel 3.793 3.793 ton Initial Pu concentration mPu/mfuel 17.7 20.2 wt.% Initial Fissile enrichment Pu39,41 14.7 16.9 wt.% Thermal Power Output Pth 80 80 MWatt Proton Beam Energy Ep 600 600 MeV Spallation Neutron Yield N(n/p) 14.51 ± 0.10 14.51 ± 0.10 n/p Net neutron multiplication M 27.80 ± 0.56 26.74 ± 0.75 Multiplication Coefficient k=(M-1)/M 0.9640 ± 0.0007 0.9626 ± 0.0010 Energetic Gain G 42.73 ± 0.88 40.64 ± 1.19 Gain coefficient G0 1.54 1.52 Accelerator Current Ip 3.20 ± 0.07 3.36 ± 0.10 mA Core Power Distributions 3 Av. fuel power density Pth/Vfuel 255 258 W/cm 3 Av. core power density Pth/Vcore 55 56 W/cm Radial peaking factor Pmax/Pave 1.25 1.21 Axial peaking factor Pmax/Pave 1.18 1.14

Future of ADS Y. Kadi 67 The PEACE : Fuel Burnup

pgpy

9 We report the variation of Global Parameters BOC EOC Units the neutron multiplication Fuel mixture (U-Pu)O2 (U-Pu)O2 coefficient after a fuel burnup Fuel mass 3.793 3.723 ton of 20 GWd/t, that is 900 days Pu concentration 17.7 16.3 wt.% of operation at 80 MW . Fissile enrichment 14.7 14.3 wt.% th Fuel burnup - 20 GWd/t 9 During this period of Cycle length - 900 EFPD operation the reactivity of the Thermal Power Output 80 80 MWatt Proton Beam Energy 600 600 MeV PEACE drops by 2.94% in Spallation Neutron Yield 14.51 ± 0.10 14.51 ± 0.10 n/p Δk, which is compensated by Net neutron multiplication 27.80 ± 0.56 14.77 ± 0.65 a factor two increase in the Multiplication Coefficient 0.9640 ± 0.0007 0.9323 ± 0.0011 accelerator current to 6.0 mA Energetic Gain 42.73 ± 0.88 21.27 ± 1.01 in order to maintain a constant Gain coefficient 1.54 1.44 power output. Accelerator Current 3.20 ± 0.07 6.00 ± 0.11 mA

Future of ADS Y. Kadi 68 The PEACE : Evolution of the reactivity for UPu fuel

1.00 20

Ip 0.99 Ksrc 18

0.98 16

0.97 14

0.96 12

0.95 10

0.94 8

0.93 6 Proton beam current, Ip (mA) Neutron Multiplication Coefficient, Ksrc Neutron Multiplication Coefficient, 0.92 4

0.91 2

0.90 0 0 100 200 300 400 500 600 700 800 900 1000 Time (days)

Future of ADS Y. Kadi 69 The PEACE : Isotopic evolution of the fuel

Variation of the UPu MOX fuel composition is plotted as a function of time

104

U-238 103 Pu-239

Pu-240 102

Pu-241 Am-241 101 U-235 Pu-242 Pu-238

100 U-236 Np-237

Radio-nuclide stockpile, (kg) stockpile, Radio-nuclide U-234 -1 10 Cm-242

Am-243 Cm-244 10-2

10-3 0 200 400 600 800 1000 1200 Time elapsed, (days)

Future of ADS Y. Kadi 70 The PEACE : Evolution of the reactivity for ThPu fuel

Future of ADS Y. Kadi 71 The PEACE : Evolution of the reactivity for ThPu fuel

Future of ADS Y. Kadi 72 The PEACE : Transmutation Rates

Plutonium incineration in ThPu based fuel is more efficient and settles to approximately 43 kg/TWh, namely 4 times what is produced by a standard PWR (per unit energy). The minor actinide production is very limited in this case.

Transmutation rates (kg/TWthh) of plutonium and minor actinides and LLFPs

EADF EADF EADF PWR Nuclides (ThPuO2) (UPuO2) (UPuO2) (UO2) ENDF/B-VI ENDF/B-VI JENDL-3.2 233 U + 31.0 Pu – 42.8 – 7.39 – 5.55 + 11.0 Np + 0.03 + 0.25 + 0.24 + 0.57 Am + 0.24 + 0.17 + 0.14 + 0.54 Cm + 0.007 + 0.017 + 0.020 + 0.044 99Tc prod + 0.99 + 1.07 +1.22 + 0.99 99Tc trans – 3.77 – 3.77 129 I prod + 0.30 + 0.31 + 0.17 129 I trans – 3.01 – 3.01

Long-Lived Fission products incineration is made possible in a very efficient way through the use of the Adiabatic Resonance Crossing Method. Such a machine could in principle incinerate up to 4 times what is produced by a standard PWR (per unit energy).

Future of ADS Y. Kadi 73 Minor Actinide Based Fuels

Minor Actinide transmutation is on the other hand very sensitive to the fuel type

1.6

1.4

1.2

1.0 MA Metal Pb-Bi cooled MA Metal Na cooled 0.8 MA Metal He cooled MA Metal + 10% Pu Pb-Bi cooled 0.6

Multiplication Factor K-eff DirtyPuMA Metal Pb-Bi cooled

0.4 DirtyPuMA Metal Na cooled

0.2

0.0

024681012141618Mass of Minor Actinides (tons)

Future of ADS Y. Kadi 74 MA Transmutation Rates

PbBi Cooled 60 Total Np

Total Pu 40 Typical transmutation Total Am rates (~ 50 kg/TWh) 20 Total Cm using MA based fuels. Total TRU 0

Doping with Pu will -20

sensibly decrease the -40 transmutation efficiency of such systems -60

-80

-100

-120 MA Metal 2.17 tons MA-Cm Metal 3.13 tons MA-Cm Metal 2.17 tons Th-12%Pu-O2 2.17 tons Th-14%Pu-O2 2.17 tons "DirtyPu" Metal 2.17 tons Th-13.5%Pu-O2 2.17 tons MA-Cm+10%Pu Metal 2.17 tons MA-Cm+10%Pu

Future of ADS Y. Kadi 75 R&D Activity in Europe

ACCELERATOR High intensity Reliability HEAT Stability TRANS- Efficiency PORT Activation SYSTEM BEAM TRANSPORT Losses Heat transfer Monitoring Thermal cycling Expansion

SHIELDING

High energy particles

REFLECTOR

Fuel fabrication SUB- MA Fuel. CRITICAL Coolant CORE Spent fuel TARGET reprocessing Neutronics Performance Window thermal stress Kinetics Failure monitor Fuel integrity Radiation effects Subcriticality Materials compatibility monitor Thermal hydraulics Liquid metal technology Maintainability

(Source:PSI)

Future of ADS Y. Kadi 76 In the FP5

PARTITIONING TRANSMUTATION PYROREP Fuels PARTNEW CONFIRM CALIXPART THORIUM CYCLE FUTURE

TRANSMUTATION Preliminary Design Studies for an Experimental ADS: PDS-XADS

TRANSMUTATION TRANSMUTATION Technological Support: Basic Studies: SPIRE MUSE TECLA HINDAS MEGAPIE-TEST N-TOF_ND_ADS ASCHLIM

Several projects have been carried out in the FP5 in the field of partitioning and transmutation. Future of ADS Y. Kadi 77 The eXperimental Accelerator-Driven System (XADS) in the 5° FP of the EU

50 MW LBE-cooled XADS 80 MW LBE-cooled XADS 80 MW Gas-cooled XADS 50 MW LBE-cooled XADS (MYRRHA)

Future of ADS Y. Kadi 78 DEMETRA: Test Facilities

STELLA Loop CIRCE Loop CEA ENEA

¾ In FP5, a complementory combination of

test facilities was CorrWett Loop VICE Loop CHEOPE Loop PSI SCK-CEN ENEA set up in Europe.

¾ EUROTRANS is fully using these TALL Loop CIRCO Loop KTH CIEMAT test facilities.

Future of ADS Y. Kadi 79 NUDATA: Experimental Facilities

GSI @ Darmstadt (Germany)

Gelina @ Geel (UE- Belgium) nTOF @ CERN (Switzerland) and its TAS γ-calorimeter

Neutron capture (n,γ) Cyclotron @ Uppsala resonances in one actinide (Sweden) Future of ADS Y. Kadi 80 R&D Activity in Europe

Future of ADS Y. Kadi 81 Open Questions

Future of ADS Y. Kadi 82 Open Questions

Future of ADS Y. Kadi 83 Why a Prototype

Future of ADS Y. Kadi 84 Why a Prototype (cnt’d)

Future of ADS Y. Kadi 85 Worldwide Programs

Project Neutron Source Core Purpose

FEAT Proton (0.6 to 2.75 GeV) Thermal Reactor physics of thermal subcritical system (k≈0.9) with (CERN) (~1010p/s) (≈ 1 W) spallation source

TARC Proton (1.5 & 2.75 GeV) Fast Lead slowing down spectrometry and transmutation of LLFP (CERN) (~1010p/s) (≈ 1 W)

MUSE DT Fast Reactor physics of fast subcritical system (France) (~1010n/s) (< 1 kW)

YALINA DT Fast Reactor physics of thermal & fast subcritical system (Belorus) (~1010n/s) (< 1 kW)

MEGAPIE Proton (600 MeV) ----- Demonstration of 1MW target for short period (Switzerland) + Pb-Bi (1MW)

TRADE Proton (140 MeV) Thermal Demonstration of ADS with thermal feedback (Italy) + Ta (40 kW) (200 kW)

TEF-P Proton (600 MeV) Fast Coupling of fast subcritical system with spallation (Japan) + Pb-Bi (10W, ~1012n/s) (< 1 kW) source including MA fueled configuration

SAD Proton (660 MeV) Fast Coupling of fast subcritical system with spallation (Russia) + Pb-Bi (1 kW) (20 kW) source

TEF-T Proton (600 MeV) Dedicated facility for demonstration and ----- (Japan) + Pb-Bi (200 kW) accumulation of material data base for long term

MYRRHA Proton (350 MeV) Fast Experimental ADS (Belgium) + Pb-Bi (1.75 MW) (35 MW)

EADF Proton (600 MeV) Fast Prototype Energy Amplifier (Europe) + Pb-Bi (4-5 MW) (100-300 MW)

Proton ( ≈ 1 GeV) Fast Reference EA Energy Production & Transmutation of MA and LLFP + Pb-Bi (≈ 10 MW) (1500 MW) Future of ADS Y. Kadi 86 Why such a delay ?

Future of ADS Y. Kadi 87 ROAD MAP FOR PEACE

2+ UO2

UO2+PuO 2

2+ PuO2 al Hi ic gh m p he ow oc el e yr fu te r p of c ac of g hn ce y in o le og s lo ra ol es gy to n oc r ch pr s Te re

Technologies of fast reactors Liquid metal targets with lead-bismuth coolant technology

Accelerator-driven nuclear waste burner

Future of ADS Y. Kadi 88 PRIORITIES

CYCLOTRON is the key choice for an ADS industry branch and represents the most sensible technology towards a successful ADS prototype ; Cyclotrons with the required performances (3-6 mA) do NOT exist today, but they are not away by big factor (1.8 mA at PSI); The choice of excellence, financially and industrially, is 50 to 100 MW ADS equipped with one or two 250 MeV cyclotrons. Such units cover through their modularity the full range of applications: from desalination, through cogeneration, to decentralised electricity production.

Future of ADS Y. Kadi 89 Priorities (cont’d)

As second priority the Thorium fuel has to be studied and its chemistry to be developed.

Reactor tests at small power and a redesign for longer operation cycles (order of 10 years) should be the third level of priority of such a project.

Future of ADS Y. Kadi 90 Phase 1 Phase 2 Phase 3

Proton Driver 250 MeV*3 mA 250 MeV*6 mA 900 MeV*6 mA Power = 0.75 MWth = 1.5 MWth = 5.4 MWth

Gain G0 0.75 0.75 2.5

Sub-criticality 0.95 0.975 0.975 level, k

Gain=Go/(1-k) 15 30 100

Thermal Power 11.25 MWth 45 MWth 540 MWth Output

Future of ADS Y. Kadi Phase 3: towards higher energies

Phase I: 44MHz Seed Cyclotron ~ 10 MWatt Phase III : 88MHz+352MHz from β=.7 Demo R&D ~ 550 MWatt (Isotopes Production Proto for Electricity Production Material Testing Facility) And Transmutation (Th fuel)

900 MeV QuickTime™ and a 250MeV TIFF (Uncompressed) decompressor are needed to see this picture.

Phase II: 44MHz Cyclotron+2nd Injector ~ 45 MWatt Proto for Local Applications (Heat,desalination)

Future of ADS Y. Kadi 92 Timeschedule

Future of ADS Y. Kadi 93 Future of ADS Y. Kadi 94 Future of ADS Y. Kadi 95 Future of ADS Y. Kadi 96 R&D Program Partnership Network Accelerator Î AIMA (F), PSI (CH), IBA (B) Spallation source Basic spallation data Î CERN (CH), GSI (D), PSI (CH) Feasibility of the windowless design Î UCL (B), FZR (D), FZK(D), NRG (NL), CEA (F) + ENEA (I) + IPUL (Latvia) Compatibility of the free surface with the proton beam line vacuum ÎSDMS (F) Subcritical assembly Î RSC “Kurchatov Institute”, Moscow – designing target – blanket systems; investigation and justification of the fuel cycle in transmutation systems, including radiochemical problems. SSC RF IPPE, Obninsk – target – blanket system construction at the SSC RF IPPE site, the functions of designer and production engineer of the element (component) base for the blanket. OKB “Hydropress”, Podolsk – Chief designer of the target – blanket system. GSPI and VNIPIET, St. – Petersburg – Design work at the SSC RF IPPE site. SSC RF _ VNIINM, Moscow – MOX fuel development and justification; IYaI RAN, Troitsk – R&D work in justification of subcritical system physics. NIKIET, Moscow – Chief designer of the equipment for the IYaI RAN site. ENEA (I), CEA (F), BN (B), UoK-UI (LT), TEE (B),CIEMAT (SP) Safety Î Robotics Î Building Î

Future of ADS Y. Kadi 97 The MMF at INR at Troisk

Future of ADS Y. Kadi 98 The MMF at INR at Troisk

Future of ADS Y. Kadi 99 The MMF at INR at Troisk

Future of ADS Y. Kadi 100 Layout of the cyclotron driver

4 MeV injector

250 MeV SSC Booster

Future of ADS Y. Kadi 101 250 MeV Booster – Phase 2

220 MHz FT cavity

Future of ADS Y. Kadi 102 Preliminary rough estimates of Equipment costs

A -Project Development and Management 10 B- Accelerators B1-Booster construction(70M$)+Assembling(15) 85 B2-Injectors (phase 1+phase 2) 8 B3-Beam lines 3 C- Shieldings 6 D-Services & Utilities 8 Power Station, Cables, Cooling station, Demin water network,etc…. Total 120 M$ 10 % Contingencies 12 M$ Grand Total 132 M$

Future of ADS Y. Kadi 103 Conclusions

Present accelerator technology can provide a suitable proton accelerator to drive new types of nuclear systems to destroy nuclear waste or to produce energy.

The Energy Amplifier, based on physics principles well verified by dedicated experiments at CERN, is the result of an optimization made possible by the use of an innovative simulation code validated in these experiments (FEAT and TARC).

An Energy Amplifier could destroy TRU through fission at about x4 the rate at which they are produced in LWRs. LLFF such as 129I and 99Tc could be transmuted into stable elements in a parasitic mode, around the EA core, making use of the ARC method.

Next step: PEACE ? when ? where ?

Future of ADS Y. Kadi 104 Conclusions

Future of ADS Y. Kadi 105