Development of a Thermal Neutron Source based on a Medical Electron Linac
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1 Development of a Thermal Neutron Source based on a Medical Electron Linac Valeria Monti December 15 th, 2016 Second Year Seminar, XXX cycle
2 Outline E_LiBANS project Physics of the thermal photo-neutron source Source installation in Turin Physics Departement Linac setting Photo-converter studies Diagnostics and on-prototype measurements Looking forward December 15th, 2016 Valeria Monti 2
3 E_LiBANS project Aim: Building an intense thermal neutrons source, with high purity levels, based on a compact linear accelerator Applications: - Irradiation of cell specimens and tissue samples for boron neutron capture therapy (BNCT) pre-clinical research - Instrument calibration - Detectors R&D Thermal neutron sources around the world: Nuclear reactors D-D/D-T sealed tubes protons accelerators radioisotopes December 15th, 2016 Valeria Monti 3
4 Thermal Photo-Neutron Source neutrons from high energy photon beams Medical high energy elinac produces photons PHOTOCONVERTER produces neutrons and moderates them to the wanted energy Experimental cavity permanently monitored by E_LiBANS project compact, reliable, safe, not expensive Specific DIAGNOSTICS qualify the produced neutron field December 15th, 2016 Valeria Monti 4
5 Photo-Neutrons Production Mechanism Electrons ~18 MeV Linac Target Linac collimators Fast neutron emission by γ,n (1-2 MeV) W/Pb neutrons detectors X-ray emission by Bremsstrahlung High Z target Photon Source Photo-converter Aim: to maximise the thermal neutrons production avoiding fast neutrons and photons contamination inside the experimental cavity December 15th, 2016 Valeria Monti 5
6 Photo-Neutrons Production Mechanism Fast neutron emission by γ,n (1-2 MeV) Electrons ~18 MeV W/Pb neutrons detectors High Z target Electron Source Electro-photo-converter Aim: to maximise the thermal neutrons production avoiding fast neutrons and photons contamination inside the experimental cavity December 15th, 2016 Valeria Monti 6
7 Reaction Features Bremsstrahlung photon spectrum at the Linac target γ,n reaction envolves only photons with E>7MeV while the linac beam has a bremsstrahlung energy distribution (γ,n) threshold γ,n cross section maximum 600 mbarn at 13 MeV, <2% of the total cross section. A huge amount of unconverted photons to be stopped. (σ (γ,n ) / σ tot ) Eγ=13.4 Mev = Gamma cross sections in Lead Conversion probability December 15th, 2016 Valeria Monti 7
8 Reaction Features γ,n reaction gives rise to fast neutrons (mean energy:1-2 MeV). These need to be slowed down to thermal energy. Moderation process implies neutrons loss by capture and escape Photo-neutron energy spectrum in 3 cm thick lead target Difficult to guide the neutrons in the wanted direction, external shield nedeed, relevant sourcecavity distance effect December 15th, 2016 Valeria Monti 8
9 Source Installation Elekta Precise Linac July 2016 commissioning of the machine in electron and photon mode completed Linac Set-up γ source: 15 MV, 18 MV, 18 MV without flattening filter Electron source: 18 MeV, 18 MeV without scatter foil December 15th, 2016 Valeria Monti 9
10 Linac parameters and k factor (γ,n) threshold Gain factor without filters: 2.2 (E> E th ) December 15th, 2016 Valeria Monti 10
11 Linac Calibration Calibration 100MU=1Gy, dose at build up in standard water phantom SSD 100 cm, Field 10x10 cm 2 CROSS BEAM PROFILES Photon beam 15 MeV with Flattening Filter Crossline Inline cm Photon beam 18 MeV without Flattening Filter cm December 15th, 2016 Valeria Monti 11
12 Radiation-Protection Measurements Project target limits <1 msv/year in control room and all other places classified as supervised area 150 Gy/week max work load Measurements in rilevant point with a Berthold Neutron Dose Rate Meter for neutron detection, scintillators and Ionisation Chambers for gamma dose All values below the limits Simulations to check dose invariance with and without neutron conversion structure Bunker door labyrinth Control room Primary barrier Linac head December 15th, 2016 Valeria Monti 12
13 Photo-Converter Beam Shaping Assembly MCNP6 simulation study in order to reduce contaminations Incident photon beam Air W +Pb target production and Lead target gamma shielding D Graphite 2 O and Graphite moderation and reflection Heavy water Boron carbide in polyepoxide Tungsten target capture of thermal neutron going Polyethylene out of the photoconverter Thin lead shield for capture Jaws collimator photons from carbon and boron December 15th, 2016 Valeria Monti 13
14 cross section (barn) cross section (barn) cross section (barn) Choice of the Target Material W-Pb Photon absorption cross section (g,n) Similar g,n microscopic cross section GDR model 0 σ abs E γ de = π e2 h Mc N Z A W Pb Neutron absorption cross section Production but ρ W = 19.2 gr/cm 3 ρ Pb = 11.3 gr/cm 3 Neutron inhelastic scattering cross section Inhelastic scattering cross section Slowing down Transparence + Gamma shield W activation problem W + n W Re + e + ν e t1 2 = 75,1 d December 15th, 2016 Valeria Monti 14
15 Photo-Converter Beam Shaping Assembly Expandable cavity for different objects exposure ( ) Possibility to expand the cavity from 3 cm to 33 cm depth with 5 cm steps, without changing the surrounding heavy water layer December 15th, 2016 Valeria Monti 15
16 Photo-Converter Beam Shaping Assembly cavity Cavity (28.6*28.6*10)cm 3 Photon beam direction W+Pb-Target (30*30*20) cm 3 Total weight c.a kg on a suitable movable support December 15th, 2016 Valeria Monti 16
17 Photo-Converter Beam Shaping Assembly December 15th, 2016 Valeria Monti 17
18 Photo-Converter Expected Spectrum Neutrons and Photons Energy Spectrum 83% 15% 2% MNCP6 simulation Standard working conditions Assuming working rate at 400 MU/min: Energy 18 MeV Electron current on target 1.05x10 14 e-/s Distance linac target photo-converter: 59 cm Fluence rate in cavity thermal (9.6 ± 0.1)*10 6 cm -2 s % epithermal (1.69 ± 0.02)**10 6 cm -2 s % fast (2.43 ± 0.07)*10 5 cm -2 s % gamma 1.05*10 6 cm -2 s -1 IAEA in air free beam parameter: D f = 1, Gy cm 2 φ th D γ = 7, Gy cm 2 φ th December 15th, 2016 Valeria Monti 18
19 Neutron Field Characterization 10 cm depth variation 5% 20 cm depth variation 14% 35 cm depth variation 26% Decrease in the first cms while cavity stretching: 25% Average thermal fluence rate decrease while cavity stretching: 35% Longitudinal profile (// to beam axis) December 15th, 2016 Valeria Monti 19
20 Neutron Field Characterization 10 cm thickness variation 5% 20 cm thickness variation 5% 35 cm thickness variation 5% Cross profile ( to beam axis) December 15th, 2016 Valeria Monti 20
21 Photo-Converter Small Prototype Measurements 9-10 September Maesurements at San Luigi Hospital 18 MV Elekta Linac Photoconverter small prototype (ca. 600 kg) Passive detectors BDT BD-PND bubble detectors Active detectors Thermal Neutron Rate Detector TNRD SiC sensors Vented ionisation chambers December 15th, 2016 Valeria Monti 21
22 Passive Diagnostics BDT BD-PND bubble detectors Working rate 100 MU/min Exposition with Cadmium cover to quantify the residual responce to fast neutrons * Dosimeters recalibration at Esther facility in Milano ** After fast dose subtraction Dosimeter Sensitivity* Bubbles/μSv Dose rate μsv/s BDT 1 Cd 0.31± ± BDT 2 Cd 0.43± ± BDT ± ±2.9** 7.6 BDT 2 2.7± ±3.0** 7.6 BDT 3 2.6± ±2.6** 7.6 PND 4 fast 0.32± ± PND 5 fast 0.31± ± Simulation Expectation μsv/s simulazioni misure December 15th, 2016 Valeria Monti 22
23 New ELiBANS Active Thermal Neutron Detectors 6 LiF deposite on different substrates 3 6 Li + n 3 1 H + α Active Unbiased Low noise ( 100 e - ) Photon insensitive Small dimension Able to work at high fluence rates TNRD SiC with Lithium deposit Vented ionisation chambers Calibrated at Hotnes Am-B source and at TRIGA reactor ENEA Casaccia metrologically qualified Pulse mode and Current mode DAQ system December 15th, 2016 Valeria Monti 23
24 TNRD response (V) TNRD response (Vs) Active Detectors Measurements Linearity of the thermal neutrons production with the linac dose rates ( MU/min) neutron production vs Linac electron current 0,25 0,2 0,15 Uniformity of the cavity center-corner difference 2% 9,6 9,5 neutron abundance vs position 0,1 9,4 0,05 9,3 9, Linac dose rate (MU/min ) 9,1 9 center up-left up-right down-right position in the cavity December 15th, 2016 Valeria Monti 24
25 Electron-Photo-Converter with e - Source air Lead Graphite Heavy water Tungsten Cavity dimension (20*20*5)cm 3 channel Ø=2 cm electrons W target --> (r=7cm) + Pb target (R tot =10cm) Electron pencil beam directly impinging the electro-photo-converter spherical target for major conversion efficiency Possibility to move the cavity out of the primary beam direction without disuniformity inconvenience (isotropy of neutron emission) December 15th, 2016 Valeria Monti 25
26 Electron-Photo-Converter with e - Source Neutrons and Photons energy spectrum 88% Standard working conditions Assuming working rate at 400 MU/min: Energy 18 MeV Frequency 200 Hz Period 2.4 μs Peak current 35 ma Electron current on target 1.05x10 14 e-/s 11% 1% D f φ th = 7, Gy cm 2 Thermal neutron flux: 1.0*10 8 cm -2 s -1 D γ φ th = 6, Gy cm 2 Enhanced thermal flux and high quality field December 15th, 2016 Valeria Monti 26
27 Conclusions and Outlook My work is devoted to the construction of an intense thermal photo-neutron source I worked on the linac installation providing simulations for the radiation-protection project and validating the results by measurements of the doses and I was involved in the machine calibration The main part of my work has been the study of the best configuration for the photo-converter in terms of geometry and materials The assembly of the final geometry is currently underway The development of active thermal neutron detectors has been successful in terms of linearity response and under high intensity neutrons fluxes A matrix of active detector is under construction to online monitor the field in the cavity of the photoconverter December 15th, 2016 Valeria Monti 27
28 Future Plan The complete metrological characterisation of the thermal neutron field for different cavity dimensions will be done and a comparison with the simulation will be studied Thermal filed characterised with the most performant active detectors among the different types under development (including comparison with a standard reference golden foils) Fast component quantified by measurements with Cd shields Gamma contamination evaluated by means of TLD diagnostics The feasibility of an electro-converter will be studied and a demonstrator will be developed The legal end of my doctorate period will be on 21 st April 2018 because of the 6 months suspension for TFA last year December 15th, 2016 Valeria Monti 28
29 Related Orals and Papers 17 International Congress on Neutron Capture Therapy, 2-7 October 2016, Columbia, Missouri 8 Yuong Researcher BNCT Meeting, 13 September 2015, Pavia, Italy E. Durisi, K. Alikaniotis, O. Borla, F. Bragato, M. Costa, G. Giannini, V. Monti, L. Visca, G. Vivaldo, A. Zanini Design and simulation of an optimized e-linac based neutron source for BNCT research, Applied Radiation and isotopes 106 (2015) K. Alikaniotis, O. Borla, V. Monti, G. Vivaldo, A. Zanini, G. Giannini Radiotherapy dose enhancement using BNCT in conventional LINACs high-energy treatment: simulation and experiment Reports of practical oncology ad radiotherapy 21 (2016) M. Costa, E. Durisi, V. Monti, L. Visca, A. Zanini and G. Giannini Neutron sources based on medical Linac Il Novo Cimento 38 C (2015) 180 DOI /ncc/i December 15th, 2016 Valeria Monti 29
30 Thank you for your attention! Elibans collaboration: INFN Torino: M. Costa, N. Amapane, E. Durisi, R. Gerbaldo, V. Monti, U.Nastasi, M. Ruspa, L. Visca, A. Zanini INFN LNF: R.Bedogni, J.M. Gomez-Ros, M. D. Sacco, M. Treccani, O. Sanchez INFN Trieste: G.Giannini, D. Treleani, M. Vascotto, K. Alikaniotis Politecnico Milano: A. Pola, D. Bortot, L. Garlati, A. Porta San Luigi Hospital and San Giovanni Bosco Hospital : S. Anglesio, U. Nastasi December 15th, 2016 Valeria Monti 30
31 IAEA Tec Doc 2001 BNCT parameters
32 Electron-mode Linac + electron-photo-converter Neutron pruduction vs W radius MCNP6 simulations in order to find the suitable material and radius of the spherical target Photon with E>6.5 MeV distribution Beam pipe shaped to have the maximum production in the centre of the sphere: Tungsten radiation length X 0 = Photons/cm2 per source particle 0.54cm, E = E 0 e x X0 Critical energy (end of bremsstrahlung domination) E cr = 9.51 MeV December 15th, 2016 Valeria Monti 32
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