y. romanets 1, r. luis 1,j. bermudez 3, j.c. david 5, d. ene 5, i. f. goncalves 1, y. kadi 2, c....

THE EURISOL MULTI-MW TARGET UNIT:RADIOLOGICAL PROTECTION AND RADIATION SAFETY ISSUES

Y. Romanets1, R. Luis1,J. Bermudez3, J.C. David5, D. Ene5, I. F. Goncalves1, Y. Kadi2, C. Kharoua2, F. Negoita4, R. Rocca2, L. Tecchio3, P. Vaz1

1ITN - Estrada Nacional 10, 2686-953, Sacavém, Portugal 2CERN- CH-1211, Genève 23, Switzerland

3INFN-LNL - Viale dell'Università, 2 - 35020 Legnaro (PD), Italy4NIPNE - Str. Atomistilor no.407, P.O.BOX MG-6, Bucharest - Magurele, Romania

5CEA - Saclay, DSM/IRFU/SPHN, F-91191 Gif-sur-Yvette, France

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Outline

The EURISOL Project Facility layout

Multi-MW Target Station

Geometry used on the simulations

Calculation results

Conclusions

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EURISOL-DS European Isotope Separation On-Line Radioactive Ion Beam Facility

The main objectives of the EURISOL Design Study were:

to show the reliability of the next-generation European ISOL Radioactive Ion Beam (RIB) facility as well as the consistence of it’s key elements: driver accelerator, target/ion-source assembly, mass-selection system and instrumentation;

to find the possible cross-interest of the scientific and research areas with other actual European projects and existing laboratory infrastructures;

to come out with the key technologies and the engineering solutions which need to evolve in order to progress on such kind of projects;

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THE EURISOL FACILITY4 MW Proton Accelerator

(1GeV, up to 4mA)Multi MW Target Station

Mass SeparatorPost Accelerator

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General layout of the Multi MW Target Station

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Facility layout including support maintenance spaces

Proton Beam

A

C

B

General view of the facility (implemented (FLUKA) geometry): A – Cut (Plane) perpendicular to the beam, include fission target handling room, RIB extraction elements, fission target end spallation target area. Cut on the point of the beam collision(z=0 cm); B – Zoom of the fission targets and spallation target area; C – Zoom of the fission targets and spallation target areas. Plane parallel to the beam (x=0 cm).

Proton beam

1 m

1 m 1.2 m

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RESULTS

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Spallation Target and Fission Targets areasNeutron and photon flux (n*cm-2

*mA-2), FLUKA performed calculationsNeutron flux

Plane z=0

Plane x=0

Photon flux

Plane z=0

Plane x=0

7 m

8 m

10 m

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Fission Targets Handling RoomNeutron and photon flux (n*cm-2

*mA-2), FLUKA performed calculations

Plane z=0cm

13 m

14 m

Neutron fluxPhoton flux

A B

Particle flux distribution in the Fission Target Handling Room during operation of the facility. Particle fluxes due leaks through the fission products extraction tubes: A – Photon flux distribution; B – Neutron flux distribution;

(n*c

m-2

*mA-2

)

(n*c

m-2

*mA-2

)

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Fission Targets Handling Room(FLUKA performed calculations)

Plane z=0cmPrompt irradiation

4MW (1GeV*4mA) proton beam

0 day (shutdown time) cooling time

Dose‐E

Q (

Sv*h

‐1)

Dose‐E

Q (

Sv*h

‐1)

Activity (Ci*g‐1), 0 day (shutdown time) cooling time

13 m

14 m

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Dose Equivalent after ShutdownDose‐EQ (Sv*h‐1)

Plane x=2cm (-1cm:1cm)Plane z=0.8 cm (-0.5cm:0.3cm)0 day (shutdown time) cooling

time

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Spallation Target and Fission TargetsNeutron flux (n*cm-2

*mA-2), FLUKA performed calculations

Plane x=0cmPlane z=0cm

1 m

1 m 1.2 m

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Activities after Shutdown (decay contribution after 200 days of irradiation (4MW power proton beam))

Activity (Ci*g‐1) Plane x=2cm (-1cm:1cm)Plane z=0.8 cm (-0.5cm:0.3cm)

0 day (shutdown time) cooling time

1 year cooling time

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Mercury Loop Trolley

Neutron flux (n/cm2/mA)

prompt irradiation, 1MW (1GeV*1mA) proton

beam

2.5 m

5 m

2.5 m

2.5 m

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Mercury Loop TrolleyActivities after Shutdown

0 day (shutdown time) cooling time

1 year cooling time

Activity (Ci*g‐1)

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Dose‐E

Q (

Sv*h

‐1)

Dose‐E

Q (

Sv*h

‐1)

Mercury Loop TrolleyDose Equivalent

Prompt irradiation, 4MW (1GeV*4mA) proton beam

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Extraction Tubes

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Extraction Tubes

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Extraction Tubes

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CONCLUSIONS

Activation – the key parameter for: Future maintenance of the facility and each sector of it Evaluation of the facility waste production (Type and quantity)

Geometry – needs particular attention on this case because: Main element of the system, extraction tubes, are the source of the

direct neutron leak Due to the necessity of exchanging/replacing various elements of the

system from time to time and to the requirements of the high safety level, the geometry becomes more complicated

Dose - determination of this value is fundamental for: Decision on choice of the access type for the different parts/sectors of the

facility Shielding requirements Conditioning/restrictions on the operation and maintenance of the facility

Project supported by the European Commission under the FP6 “Research Infrastructure Action- Structuring the European Research Area” EURISOL-DS Project Contract no. 515768 RIDS. Part of the work has also been supported by the Portuguese Foundation for the Science and Technology (FCT) in the framework of the projects CERN/FP/83586/2008 and POCI/FP/81951/2007

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Thank you

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