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The EURISOL Multi-MW Target Unit: Radiological protection and radiation safety issues

The EURISOL Multi-MW Target Unit: Radiological protection and radiation safety issues. Y. Romanets 1 , R. Luis 1 ,J . Bermudez 3 , J.C. David 5 , D. Ene 5 , I. F. Goncalves 1 , Y. Kadi 2 , C. Kharoua 2 , F. Negoita 4 , R. Rocca 2 , L. Tecchio 3 , P. Vaz 1

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The EURISOL Multi-MW Target Unit: Radiological protection and radiation safety issues

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  1. 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), Italy 4NIPNE - Str. Atomistilor no.407, P.O.BOX MG-6, Bucharest - Magurele, Romania 5CEA - Saclay, DSM/IRFU/SPHN, F-91191 Gif-sur-Yvette, France • SATIF-10, CERN • 2-4 June 2010

  2. Outline • The EURISOL Project • Facility layout • Multi-MW Target Station • Geometry used on the simulations • Calculation results • Conclusions

  3. EURISOL-DS • European Isotope Separation On-LineRadioactive 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;

  4. 4 MW Proton Accelerator (1GeV, up to 4mA) Multi MW Target Station Post Accelerator Mass Separator THE EURISOL FACILITY

  5. General layout of the Multi MW Target Station

  6. Facility layout including support maintenance spaces Proton Beam

  7. A 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). C 1 m Proton beam 1 m 1.2 m B

  8. RESULTS

  9. Spallation Target and Fission Targets areas Neutron and photon flux (n*cm-2*mA-2), FLUKA performed calculations Photon flux Neutron flux Plane z=0 Plane z=0 8 m 7 m Plane x=0 Plane x=0 10 m

  10. Fission Targets Handling Room Neutron and photon flux (n*cm-2*mA-2), FLUKA performed calculations 14 m Plane z=0cm 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; 13 m Photon flux Neutron flux (n*cm-2*mA-2) (n*cm-2*mA-2) A B

  11. Fission Targets Handling Room (FLUKA performed calculations) Prompt irradiation 4MW (1GeV*4mA) proton beam 14 m Plane z=0cm 13 m Dose‐EQ (Sv*h‐1) 0 day (shutdown time) cooling time Dose‐EQ (Sv*h‐1) Activity (Ci*g‐1), 0 day (shutdown time) cooling time

  12. Dose Equivalent after Shutdown Dose‐EQ (Sv*h‐1) 0 day (shutdown time) cooling time Plane z=0.8 cm (-0.5cm:0.3cm) Plane x=2cm (-1cm:1cm)

  13. Spallation Target and Fission Targets Neutron flux (n*cm-2*mA-2), FLUKA performed calculations Plane z=0cm Plane x=0cm 1 m 1 m 1.2 m

  14. Activities after Shutdown (decay contribution after 200 days of irradiation (4MW power proton beam)) Activity (Ci*g‐1) Plane z=0.8 cm (-0.5cm:0.3cm) Plane x=2cm (-1cm:1cm) 0 day (shutdown time) cooling time 1 year cooling time

  15. Mercury Loop Trolley 2.5 m Neutron flux (n/cm2/mA) 5 m prompt irradiation, 1MW (1GeV*1mA) proton beam 2.5 m 2.5 m

  16. Mercury Loop Trolley Activities after Shutdown Activity (Ci*g‐1) 0 day (shutdown time) cooling time 1 year cooling time

  17. Mercury Loop Trolley Dose Equivalent Prompt irradiation, 4MW (1GeV*4mA) proton beam Dose‐EQ (Sv*h‐1) Dose‐EQ (Sv*h‐1)

  18. Extraction Tubes

  19. Extraction Tubes

  20. Extraction Tubes

  21. 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) • 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 • 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 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

  22. Thank you

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