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EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH CERN BEAMS DEPARTMENT

Geneva, Switzerland November, 2009

CERN-BE-Note-2010-002

EURISOL High Power Targets

Yacine Kadi1, Jacques Lettry1, Mats Lindroos1, Danas Ridikas2, Thierry Stora 1, Luigi Tecchio3

1 CERN Geneva, Switzerland

2 CEA Saclay, France 3 INFN Legnaro, Italy

Abstract

Modern Nuclear Physics requires access to higher yields of rare isotopes, that relies on further development of the In-flight and Isotope Separation On-Line (ISOL) production methods. The limits of the In-Flight method will be applied via the next generation facilities FAIR in Germany, RIKEN in Japan and RIBF in the USA. The ISOL method will be explored at facilities including ISAC-TRIUMF in Canada, SPIRAL-2 in France, SPES in Italy, ISOLDE at CERN and eventually at the very ambitious multi-MW EURISOL facility. ISOL and in-flight facilities are complementary entities. While in-flight facilities excel in the production of very short lived radioisotopes independently of their chemical nature, ISOL facilities provide high Radioisotope Beam (RIB) intensities and excellent beam quality for 70 elements. Both production schemes are opening vast and rich fields of nuclear physics research. In this article we will introduce the targets planned for the EURISOL facility and highlight some of the technical and safety challenges that are being addressed. The EURISOL Radioactive Ion Beam production relies on three 100 kW target stations and a 4 MW converter target station, and aims at producing orders of magnitude higher intensities of approximately one thousand different radioisotopes currently available, and to give access to new rare isotopes. As an illustrative example of its potential, beam intensities of the order of 1013 132Sn ions per second will be available from EURISOL, providing ideal primary beams for further fragmentation or fusion reactions studies. Published in Nuclear Physics News, Vol. 18, No. 3, 2008. Subject: Targets for EURISOL key words: Radioisotopes beams, high power targets, EURISOL, safety.

facilities and methods

Vol. 18, No. 3, 2008, Nuclear Physics News 21

EURISOL High Power Targets

Introduction Modern Nuclear Physics requires

access to higher yields of rare iso-topes, that relies on further develop-ment of the In-flight and IsotopeSeparation On-Line (ISOL) produc-tion methods. The limits of the In-Flight method will be applied via thenext generation facilities FAIR in Ger-many, RIKEN in Japan, and RIBF inthe United States. The ISOL methodwill be explored at facilities includingISAC-TRIUMF in Canada, SPIRAL-2in France, SPES in Italy, ISOLDE atCERN, and eventually at the veryambitious multi-MW EURISOL facil-ity [1]. ISOL and in-flight facilitiesare complementary entities. While in-flight facilities excel in the productionof very short lived radioisotopes inde-pendently of their chemical nature,ISOL facilities provide high Radioiso-tope Beam (RIB) intensities andexcellent beam quality for 70 ele-ments. Both production schemes areopening vast and rich fields of nuclearphysics research.

In this article we will introduce thetargets planned for the EURISOL facil-ity and highlight some of the technicaland safety challenges that are beingaddressed. The EURISOL RadioactiveIon Beam production relies on three100kW target stations and a 4MW con-verter target station, and aims at pro-ducing orders of magnitude higherintensities of approximately one thou-sand different radioisotopes currentlyavailable, and to give access to new rareisotopes. As an illustrative example ofits potential, beam intensities of theorder of 1013 132Sn ions per second willbe available from EURISOL, providingideal primary beams for further frag-mentation or fusion reactions studies.

Direct High Power ISOL Targets Classical ISOL targets are operat-

ing for more than four decades. Inorder to open the fission, spallation,and fragmentation reaction channels,the target material is directly exposedto energetic charged particle beams ofprotons or light ions. This method hasproven to be very successful; around1,000 radioisotope beams of 70 differ-ent chemical elements have been pro-duced with driver beams energiesranging from 40 MeV/A to 1.4 GeV/Aat ISOLDE-CERN-Geneva, RIBF-Oak Ridge, TRIUMF-Vancouver, andISIS-Gatchina. The crucial need forchemical purity and the presence ofisobars with orders of magnitude moreintensity, due to their relative proxim-ity to stability, lead to the develop-ment of various types of chemicallyselective ion-sources, molecular sidebands, and active transfer lines.

Today, 100 target-transfer-line-ion-source systems are operated rou-tinely at with both pulsed (1–4 kW)and quasi DC (up to 10–35 kW)driver beams. The main challenge setby the 100 kW EURISOL beampower, is that the evacuation of theenergy deposited by the 1 GeV pro-tons through ionization in the targetmaterial, while the target materials(some of which are low density andopen structure materials or are in theform of oxides with thermal insulat-ing properties) are kept at the highestpossible temperature to minimize thediffusion time of the radioisotopes.The target oven is designed to opti-mize the pumping speed. TheEURISOL ion-source and transferlines are designed to efficiently ion-ize larger amounts of radioisotopes inthe presence of an increased flow of

impurities released by larger amountsof target materials.

The life time of the target, transfer-line, and ion-source system is a keyissue that directly impacts on theavailability of the facility via the ratioof the time required to change the tar-get-ion-source unit and to tune thebeam, versus the radioactive beamoperation time (typically a total of10 days). Today’s target-ion-sourceunit’s life time is 1.5 1019 protons whenoperated in pulsed mode at 1.4 GeV,and reaches 3.2 1020 protons underquasi cw operations with 0.5 GeV pro-tons (EURISOL: 5.4 1019 1 GeV pro-tons per 100 kW beam day). This, andthe need to deliver different ion-beamsto several users in parallel, motivatedthe choice of three independent100 kW direct target stations.

High temperature sintering, graingrowth, and radiation damagesinduced by the driver beam on the tar-get material, its container and ionsource components, are the likely fac-tors limiting the life time of the targetand ion-source system. The effectswill be increased decay losses as wellas the reduction of yields and ion-source efficiency. Four target and ion-source systems were selected in theEURISOL design study in order tobenchmark the necessary R&D fieldsand to validate the necessary engineer-ing and numerical simulations tools.

Heat transfer. With depositedpowers of the order of 10 to 60 kW,efficient and novel heat dissipationschemes must be developed. For oxidetargets—otherwise known as thermalinsulators—this is addressed by thedevelopment of new composite mate-rials such as a niobium-foil– alumi-num oxide compound. For molten


22 Nuclear Physics News, Vol. 18, No. 3, 2008

metal target units, circulation loopsand heat exchangers will handle theheat load, where the release propertiesrely on the appropriate design of anisotope diffusion chamber with mini-mal drop size or liquid layer thickness.

Multi-body target. Efficient heatdissipation is achieved at TRIUMF fora primary beam power of 20 to 50 kW.Several compact sub-units of the sametype, each accommodating ~25 kW,will successfully address the heatdeposited by a 100 kW driver beam(Figure 1). The release properties areinfluenced by the merging of the neu-tral atomic streams from the sub unitsinto a single ion source, through shorttransfer lines. The target life time isslightly affected by the pulsed protonbeam time structure inherent to thedistribution of the p-beam to each subunit. To benchmark the release, a dualcontainer target equipped with two

transfer lines and remotely actuatedtight valves has been tested with anoble gas ion source at ISOLDE. Themeasured release reproduces theexpected effusion delay originatingfrom a fraction of the isotopes revisit-ing the second transfer line and target.As it is known for many elements, the

diffusion process is dominating therelease. The first results on Ar and Neradioisotopes are promising.

Radiation induced materialdamage. The Target Prototypes Irra-diation Programme for EURISOL(TARPIPE) is ongoing at Injector 1 atthe Paul Scherrer Institute. Samples ofmetals, carbides and oxides were irra-diated in order to reach several dis-placements per atom (dpas), whichcorresponds to 3 weeks of target oper-ation at nominal EURISOL parame-ters. Visual and microscopicobservation of the material before andafter irradiation will allow assessingsintering and irradiation effects atnominal operation temperatures.

Diffusion. New submicrometricand nanometric target materials areunder development, where their stabil-ity at high temperature and underintense irradiation is a critical feature.A first milestone has been achievedwith the successful development ofsubmicrometric SiC targets (Figure 2),which has produced the highest andmost stable yields of exotic Na andMg isotopes at CERN-ISOLDE.

Ion-sources and effusion. The ionsources tested with one order of magni-tude increase of the stable ion current,kept their efficiencies. For the more

Figure 1. The EURISOL 100 kW multi-body direct target concept, four targetsare connected to a single ion-source. The proton beam is sequentiallydistributed on each target.

Figure 2. Micrograph of a sub-micrometric SiC target before (left) and after(right) in-beam operation at CERN-ISOLDE.



complex target-ion-source systems thathave been proposed, the effusion timewill increase. Very short lived elementswill still require dedicated systems.

Direct target yields. The produc-tion cross-sections of the 100 kW tar-get stations are the same as thosefound at ISOLDE (1 GeV). Theyields of neutron rich radioisotoperesulting from fission reactions arenot very sensitive to the protonenergy between 0.5 and 1.4 GeV;however, evaporation is larger withincreasing proton beam energy andenhances the production in the n-deficient and deep spallationdomains. Light fragments arestrongly enhanced with increasingproton energy (i.e., yield increases ofseveral orders of magnitude weremeasured for light sodium isotopesbetween 600 MeV and 1.4 GeV atISOLDE). Within the EURISOLframework, the direct target RIBintensities are expected to be propor-tional to the driver beam power.

Neutron Converter ISOL Targets The neutron converter ISOL con-

cept was first proposed by Jerry Nolenand co-workers. In an ISOL converter

system, the neutrons are generated byhigh energy protons impacting on ahigh Z material (so-called spallationn-source). The radioisotopes are thefission products of fissile target mate-rial positioned close to the neutronsource. The “low” temperature con-verter is also designed to convey theheat resulting from the primary parti-cle’s ionization losses to dedicatedheat exchangers. In order to cope withthe 2.3 MW power deposited in thespallation target, out of the 4 MWEURISOL proton beam, it has to bemade of liquid metal. Two optionsbased on axial or radial molten metalflow directions were investigated. It isinteresting to note that, for a given Hgtemperature increase (typically 120–180 K), a radial flow allows one orderof magnitude higher power density.

Converter with Liquid Metal in Contact with a Window

In the Coaxial Guided Stream(CGS) design, the mercury is keptunder pressure and flows within adouble walled tube with a proton beamwindow at one end (Figure 3). The mer-cury flows toward the proton beam inthe outer part of the tube and along the

p-beam in the inner part making a u-turn at the window. By choosing mer-cury, which is an excellent spallationtarget and is liquid at room tempera-ture, this liquid metal can transportaway a huge amount of heat, and atthe same time cool the target walls andthe window. The radioactivity inducedin the mercury can to some extent beremoved, with some of the extractedisotopes having a commercial value.

The energy deposition peaks atapproximately 2 cm after the interac-tion point, reaching 1.9 kW/cm3/MWof beam, and decreases rapidly there-after. The beam window is enduringmust withstand 900 W/cm3/MW ofbeam. The window parameters wereoptimized using an interative processin which the temperature and thermalstress in the window were calculatedto be below irradiated materials stresslimits. Once the beam window wasoptimised, the liquid mercury flowinside the target container was tunedto minimise pressure losses whileensuring adequate cooling of thewindow and preventing vaporizationand cavitation in the back-swept sur-faces. Eventually, annular blades wereinserted along the beam window to

Figure 3. Coaxially Guided Stream Hg-spallation neutron source designed for the 4 Mw target station of the EURISOLfacility, the expected Hg-flow velocities are indicated on the detailed view of the 180° turn.



accelerate the flow, increase the localcooling and reduce the pressure drop atthe 180-degrees turn. With this design,and a bulk pressure of 7.5 bar, the max-imum temperature in the beam windowis 200°C and the maximum von-Missesstress is 135MPa. The mercury peaktemperature is 180 °C and its maximumvelocity is 6 m/s at the 180-degreesturn, in the channels formed by theflow-guides and the walls.

A Windowless Liquid Metal Converter The so-called Windowless Trans-

verse Mercury Film (WTMF) target(Figure 4) avoids the technical diffi-culties related to pressurized beamwindows and is advantageous in termsof neutronics. Mercury flowingthrough the upper tube is guided into avertical jet by sets of fins. Below theinteraction point, the mercury isrecovered and pumped to the heatexchanger circuit, where the volatileseparator and the mercury reservoirare placed.

The brief exposure of the liquidmetal to the proton beam permitscontrol of the temperature increase bysetting the local velocities via tuningof the fin pitches to match the beamcooling requirements. The WTMF

target was evaluated for a mercuryflow-rate of about 12 l/s; a tempera-ture increase of the mercury of about117.5 K; a heat deposition density onthe beam centre line of 25 kW/cm3;and a total heat deposition of 2.3 MW.The film is split in two regions, a cen-tral one (1 cm thickness), receiving theimpact of the beam and flowing at highspeed, and an external one confiningthe former (1.5cm on each side) toreduce high-energy secondary particles

escape and maximize the productionof spallation neutrons.

Three different prototypes weretested on an Indium-Gallium-Tin loopat the Institute of Physics and the Uni-versity of Latvia (IPUL, Riga). Thefilm behavior and flow stability seem apriori compatible with the EURISOLdesign requirements, although furthertests, involving larger mass flows,have to be performed. In order to testthe feasibility of the WTMF design, ascale model is being developed andwill be tested with mercury.

The beam-target interaction as afree surface facilitates operation overextended periods; a reduction of thetarget exchange frequency (due tobeam window radiation damage) isanticipated. Moreover, the reducedthickness of the film produces a harderneutron spectrum and permits thepositioning of actinide fission targetscloser to the interaction point. Thisincreases the fission density rates andreduces the higher actinide produc-tion, by favoring fission rather thancapture reactions.

Figure 4. Windowless Metal Transverse Flow (WMTF) spallation neutronsource. Three pitch flow-guide racks were designed to match the Hg-flow to thedriver beam deposited power density illustrated by the lego plot.

Figure 5. Fission target assembly (left); Details of the finned target, maximizingheat dissipation, and its thermal equilibrium calculation are shown (right).



Fission Target EURISOL-DS targets are derived

from the concept proposed by thePIAFE (Projet d’Ionisation et d’Accel-eration de Faisceaux Exotiques) andMAAF (Munich Accelerator for FissionFragments) projects. Conceptually, atarget filled with 235U or other actinide isinserted, through a channel created in theshielding, close to the neutron source atthe position of maximum neutron flux.Each target module can be inserted,replaced and serviced by means ofremote handling. The shielding aroundthe n-spallation source is a combinationof iron and concrete with a total thick-ness of about 6 meters. The neutron fluxis thermalized in order to optimize 235Ufission while for other fissionable targetmaterials, like 238U or 232Th, a hard neu-tron spectrum is required. Up to six ver-tical channels are foreseen each

containing MAAF-like production sys-tems. Loading and unloading all beamelements, including the fission targets, isaccomplished within a mobile transporttube. The assembly is then moved into ahot cell where remote handling of thecomponents will be performed undervisual control.

In operation position, all compo-nents are inside a double walled vac-uum tube embedded in the concreteshielding. A cooling water system isrequired to evacuate the fission heat of30 kW that correspond to 1015 fissionsper second. In view of the radiationlevels, vacuum pumps have to beplaced after the shielding. In order toevacuate the gases continuously ema-nating from the fission target duringoperation, cryo-panels are distributedinside the vacuum tube. The systemnot only improves the vacuum but also

traps and confines the radioactivityfrom gaseous elements.

The MAAF fissile material ishighly enriched uranium dispersed inthe graphite matrix with a 235U-densityof 2g/cm3. To host 235U, two graphitetypes were selected in view of theirthermal properties: MKLN (specialgraphite) and POCO (graphite foam).High density uranium-carbide (UC)pellets containing 238U, enriched withabout 2% of 235U, has a total U-densityof 12 g/cm3. An intensive R&D pro-gram to characterize the RIB-yields ofhigh density uranium-carbide has beencarried out in collaboration with sev-eral European Institutions.

The target assembly is shown inFigure 5. The actinide carbide disks arehoused in a graphite primary container,200mm long and 35 mm diameter, sur-rounded by a tantalum container actingas confinement and as heat radiator.This container has a finned structurethat increases its effective emissivityand allows the active target volume toremain at the required high temperatureof around 2000 °C, while the tempera-ture drop is mainly localized across thefins. A central hole of 8 mm diameterlinks to single ionization ion sources(laser, plasma, ECR) that are underinvestigation. The fission target hasbeen designed to operate at 100 kV.

Fission target yields. The flexibleapproach resulting from the multi-fissiletargets inspired from the MAAF-PIAFEprojects, allows neutron spectra fromthermal to hard and the choice of suit-able actinides. The isotope productioncharts are under investigation; the vari-ous options yield up to orders of magni-tude differences in specific cross-sections (illustrated by the difference ofthermal neutrons induced 235U fissionvs. hard neutron driven 238U fission).The individual target units are to bedesigned to handle 1015 fission/s for a

Concrete, 0 degree, at 1m70

Ca41

Ar39

H3

Fe55

Ca45Ar37

Total

Figure 6. Time evolution of the specific activity of the shielding concrete afterforty years of operation. In this simulation, 2.3 MW are deposited in the Hgneutron spallation source, out of the 4 MW average beam power.



235U targets in a thermal neutrons flux.Reduction of the fission rate by oneorder of magnitude is expected for otheractinide targets used with hard neutrons.

The release time is driven by diffu-sion and effusion. Therefore, the decaylosses will be given by the chosenactinide, its isotopic distribution, stochi-ometry, mass, and geometry. As a firstapproximation, in view of the similaractinide masses and target volumeinvolved, the typical release parameters(and decay losses) should be close tothose of standard ISOLDE UCx targets.

The ion-sources will be dealingwith 3 orders of magnitude higherradioactive beams and higher stableelements streams than today’s systems.Further work is required to assess theMulti-MW fission target ionizationefficiencies. The ion beams of this tar-get and ion-source multi-systems needsto be merged, a proposition based on anopen ECR structure is under investiga-tion, while seemingly promising, itsefficiency is not yet determined.

Safety for High Power ISOL Targets

The envisaged EURISOL facilitywill produce RIBs at intensities 2–3orders of magnitude higher than exist-ing facilities. A corresponding increaseof the radioactive inventory is expectedthat requires a dedicated safety filecontaining procedures, hazard evalua-tion, risk analysis, operational safetythat should be in the foreground fromthe very first design, to the dismantlingof the facility including disposal of theradioactive waste. The selection of theproduction methods, the choice ofmaterials and the design of the facilitymust be integrated from the start. Thesafety aspects of the future RIB pro-duction targets and transport system,among them, the fissile targets aimingat a few 1015 fissions/s, will bear the

highest activity and shall integrate thebest safety standards. The new RIBproduction techniques will be keyinputs to the safety approval proce-dures and will have a major impact onthe final cost of the entire facility.

Spallation neutron source.EURISOL relies on a high-energy high-intensity proton accelerator coupled tothe high power liquid Hg target. Thisresults in a comparable nuclear installa-tion to the new generation spallationneutrons sources SNS (Oak-Ridge,USA) and J-SNS (J-PARC, Japan).

Fission products. The fissile mate-rial RIB production targets will useeither uranium or thorium, leading toan in-target thermal fission power com-parable to low power research reactors.

Confinement. Radioactive nucleibeams of unprecedented intensities upto 1013 ions/s will be extracted, ionized,and post-accelerated up to the energiesof 150 MeV/u and distributed overlarge areas to the experiments. In viewof these mobile and quickly transportedsources, ensuring the radioprotection ofthe staff in the experimental hall will bea major challenge. Furthermore, non-ionized gaseous/volatile radioactivity isfreely traveling in the beam pipes andvacuum system and must be monitored,controlled, and managed.

Dose rates. Much of the safetywork has focused on the Multi-MW tar-get station—the most challenging issuein this context. The characterization ofprompt radiation from primary beamcomponents, target-converter, RIB pro-duction targets, beam dump, and sec-ondary beam lines is being assessed.The activation of the entire environ-ment including buildings, air, soil, andground water have been estimated. Theprompt and residual dose levels are cru-cial inputs to the dimensioning of thebuildings and appropriate shieldingstructures, for defining the maintenance

procedures and accessibility levels, andfor preparing dismantling and decom-missioning strategy. As an example, theresidual specific activity of the concreteshielding is shown in Figure 6.

Radioactive waste disposal. Thehandling and disposal of the radioac-tive production targets (e.g. UCx,ThCx), the liquid Hg converter targetand its auxiliary systems is not yetstudied. Our estimates show that theinduced radioactivity of the Multi-MW target station reaches approxi-mately 109 GBq. This implies that theradioactivity handling and the preven-tion of release accidents should becomparable to the nuclear powerindustry. At the end of EURISOLoperations, the irradiated liquid mer-cury (~20 tons) has to be treated ashighly radioactive waste. The onlyappropriate final disposal form for thisradiotoxic and toxic type of waste issolidification. Therefore, we launchedboth theoretical and experimental ded-icated studies on solidification of mer-cury, aimed at the selection of anadequate sythesis and of a matrixsuited for its final disposal.

Radioactive gases. 1015 fissions/salso yield sizable amounts of volatileradioactive species that have to be con-fined. For this purpose, the concept of acryo-trap system placed between theproduction target and the experimentalarea has been proposed, designed andtested to freeze gaseous radioactivity asclose to its origin as possible. The stud-ies converged on the design of a com-pact cryo-trap operated with coldhelium gas at a saturation temperaturearound 18 K, with a volatile radioactiv-ity retention capability of 99.98%.These design goals have been experi-mentally verified with two differentprototype cryo-traps. One of thesesolutions will be implemented in thebeam line design of EURISOL.



Alpha emitters. Direct irradiationof actinide targets with high-energy,high-intensity protons results in theproduction of volatile long-lived alphaemitters. The most obvious is radonthat itself conveys little radiologicalhazard, but decays into products (theso-called radon progeny) of consider-able radio-toxicities such as 210Po. Thedose per unit intake of activity ofalpha-particle emitters, is approxi-mately 1,000 times that of beta/gamma-emitting radio-nuclides. Theinstallation should be equipped withdedicated monitoring systems andprocedures to keep under control thealpha radioactivity levels.

Critical group. The critical groupexposure via complex pathways,including the air, water, and food chainboth in normal operation and accidentalsituations must be investigated. For thispurpose, a dedicated EURISOL Toolkitwas created, which gathers the relevantinformation and source data as well asother information or methods alreadyvalidated, accepted, and recommendedby national and international regulatorybodies. This toolkit includes models forassessing the health and environmentalimpact of nuclear facilities that aresuitable for research nuclear reactorsand high-power high-energy particleaccelerators. The EURISOL Toolkit isbeing tested and will be applied for aselected case study characteristic forthe EURISOL Multi-MW target sta-tion, leading to the environmentalimpact assessment both in normaloperation condition as well as in acci-dental situations.

Eventually, we would like to stressthat safety and radioprotection aspectsof the future high power ISOL targetsmust be addressed at the very concep-tual stage of the design studies. TheEURISOL design study is a goodexample of this approach.

Discussion and Conclusion Development and engineering.

New target arrangements or materialsaiming at improved heat dissipation orconduction (ISOLDE, TRIUMF), long-term stability (high density UC, PNPIGatchina) or release properties SiC(ISOLDE) were successfully developed.Synthesis of new UCx materials withimproved mechanical properties areunder development at INFN-LNL andwill be evaluated for RIB productionboth at ISOLDE and within the SPESproject. Innovative solutions were pro-posed for windowless neutron spallationsources, modular actinide targets,atomic beam merging in ion-sources,and radioactive ion-beam merging inopen ECRs that are all mandatory assetsfor future high intensity RIB facilities.

Figure of Merit of the EURISOLFacility. The potential of theEURISOL facility in producing 1,000different radio-isotopes, with two tothree orders of magnitude yieldincrease, is within reach. The cross-sections are well known; the decaylosses were extensively measured andassessed; the ion-source efficienciesare confirmed or improved via devel-opments of Resonant Ionization Laserion-source based on solid state lasers;and improvement in release time wereobtained and are still to be expectedwith increasing experience in the engi-neering of new materials. New reac-tion channels become de factoavailable; in dedicated modular unitscoupled to the neutron spallationsource with the n,x reactions such asthose explored at Louvain-La-Neuve,or being developed at the futureSARAF accelerator at Soreq NRC.

Safety. Safety integration from thestart hints to the need of innovative andflexible solutions in matters of safety.While EURISOL has similarities tohigh-power spallation n-sources and to

small research reactors, the use of hightemperature pyrophoric actinide car-bide targets, the presence of alphaemitters and the distribution overextended buildings of intense radioac-tive beams and sources of all chemicalnatures, is very specific and requiresdedicated technical standards that willhave to be applied under utmost reli-able safety rules and procedures.

The ambitious targetry goals set bythe EURISOL study group [2] are beingeffectively addressed within theEURISOL-Design Study; this globaltargetry and safety effort involved closeto 200 scientists and technicians across40 institutes from 22 countries. Theircrucial contributions in delivering inno-vative solutions and relevant technicaldevelopments are herby acknowledged.Furthermore, a wide dissemination ofinformation took place, its apex beingthe training of many young scientists inthe most effective manner, namely viathe simulation and realizations of proto-types tested in realistic conditions atoperational RIB facilities.

YACINE KADI, JACQUES LETTRY, AND

MATS LINDROOS

CERN

DANAS RIDIKAS

CEA

THIERRY STORA

CERN

LUIGI TECCHIO

INFN

References 1. http://www.eurisol.org and references

therein. 2. “The EURISOL report,” Ed. J. Cor-

nell, GANIL, Caen, 2003, Europeancommission contract No. HPRI-CT-1999-500001.

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