1. Determination of gamma dose component in thermal column of Pavia Triga reactor by using alanine ESR detectors Saverio Altieri Department of Physics University of Pavia, Italy and National Institute for Nuclear Physics (INFN)

2. BNCT preclinical studies at Pavia Triga reactor research of new boron carrier boron carrier up-take measurements in vitro and vivo in animal models test of effectiveness and toxicity of BNCT by irradiation of cell cultures, and animal model of rats and mice treated with new boron compounds Irradiation position Li-6 neutron shields low gamma dose irradiation position

3. Characterization of the irradiation position: neutron flux nuclear reactor broad energy spectrum Energy rangeDetectorTechnique Thermal (< 0.5 eV) 1/v detectorCd + bare foils Epithermal (0.5 eV – 10 keV) Resonance detector Multifoil set-up Fast (> 10 keV) Threshold detector B + covered foil multifoil activation + unfolding algorithm Protti et al., Transactions of the American Nuclear Society, San Diego, California, November 11-15, 2012

4. Characterization of the irradiation position: microdosimetry gamma Dose components neutrons BNCT Colautti et al., Applied Radiation and Isotope (2013) microdosimetric measurements (mini-TEPC LNL )

5. Characterization of the irradiation position: gamma dose in collaboration with University and INFN of Palermo Alanine dosemeters Irradiation channel

6. Simulations of photon background and dose components MCNP in the alanine detectors

7. Simulations of photon background and dose components MCNP

8. Simulations of photon background and dose components MCNP CPE and calibration

9. Characterization of the irradiation position: CPE

10. Characterization of the irradiation position: calibration Radiotherapy unit in Palermo

11. Characterization of the irradiation position: calibration at radiotherapy unit in Palermo

12. Characterization of the irradiation position: gamma dose Thermal neutron attenuation 10 -3

13. Characterization of the irradiation position: gamma dose

17. using non shieded data

18. Characterization of the irradiation position: gamma dose and putting RE = 0.4 for thermal neutron POS 1Sim34.82 Gy Exp36.76 Gy POS 2Sim14.27 Gy Exp14.13 Gy POS 3Sim6.89 Gy Exp6.29 Gy

19. Characterization of the irradiation position: conclusions  Using alanine dosimiters we were able to measure gamma dose in a mixed field (thermal neutron + gamma)  The separation of gamma dose from thermal neutron one was possible thanks to the lithium carbonate shield  We evaluated the alanine RE value for thermal neutrons

20. Italian BNCT network  University and INFN of PAVIA  University of PALERMO  University of TORINO  University of Piemonte Orientale  University of FIRENZE  Universitiy of POTENZA  Oncological Institute of Veneto (IOV)  LNL-INFN International collaborations  CNEA, Argentina: very active researchers exchange for computational dosimetry, treatment planning, beam design, B concentration measurement methods inter-comparison  INL, Idaho, USA: neutron spectrometry in irradiation facilities http://www.bnct.it

21. Thank you for your attention

22. Simulations of photon background and dose components MCNP