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LIBRA Kick-off meeting, March 11, 2009 Large Sample NAA and Bio-Medical Applications at the Tandem accelerator F. Tzika, D. Vasilopoulou, D. Kontogeorgakos, A. Savidou and I.E. Stamatelatos Research Reactor Laboratory Institute of Nuclear Technology & Radiation Protection, NCSR "Demokritos", Greece ΔΗΜΟΚΡΙΤΟΣ
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LIBRA Kick-off meeting, March 11, 2009 Motivation Presentation of an outline of our group’s research activities at the Research Nuclear Reactor Laboratory Explore possibilities of interaction between our group and the TANDEM accelerator laboratory through LIBRA
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LIBRA Kick-off meeting, March 11, 2009 Research Activities Biomedical applications of INAA (extra-cellular body space in children with severe burn trauma, serum aluminum levels in patients in chronic renal dialysis) Development of a Large Sample NAA method at the research reactor for cultural heritage, environmental and industrial applications Large Sample Prompt Gamma NAA methods using isotopic neutron sources for small animal body composition studies and Non-Destructive Testing of materials Monte Carlo simulations for criticality safety, radioactive waste management and radiation protection and nuclear instrument design
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LIBRA Kick-off meeting, March 11, 2009 Unique Applications: Analysis of precious objects (i.e. cultural heritage studies) Analysis of inhomogeneous samples (sediment, e-waste) Industrial (analysis of whole components) Large Sample Neutron Activation Analysis
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LIBRA Kick-off meeting, March 11, 2009 LSNAA method Thermal neutron self-shielding within the sample Tzika et al, 2005 HPGe detector efficiency 20cm 40cm
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LIBRA Kick-off meeting, March 11, 2009 LSNAA of a ceramic vase Experiment performed at Reactor Institute Delft
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LIBRA Kick-off meeting, March 11, 2009 Radiological Characterization of materials for Fusion Nucl. Instr. Meth B, 2005 Hands-on limit Recycling limit Elemental composition of first wall material (+ trace element impurities) SiC/SiC and EUROFER experimentally determined by NAA Neutron spectrum at the first wall of a fusion device calculated using MCNP code Contact dose-rate decay prediction using EASY code after 5 y of irradiation at 1 MW/m2 load SiC f /SiC
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LIBRA Kick-off meeting, March 11, 2009 Large Sample Prompt-Gamma NAA using isotopic sources Element Prompt (MeV) Reaction N10.83 14 N(n, ) 15 N Ca6.42 40 Ca(n, ) 41 Ca Cl6.11 35 Cl(n, ) 36 Cl H2.22 1 H(n, ) 2 H Nucl. Instr. Meth B, 2007 Small animal body composition studies Water Fat Protein Bone ash Four compartment model
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LIBRA Kick-off meeting, March 11, 2009 Body Composition: Advanced Compartment Models CompartmentMeasured Element ReactionMethod Protein (=6.25xN)N 14 N(n, ) 15 N, E =10.83 MeV PGNAA Extra-cellular spaceCl 35 Cl(n, ) 36 Cl E =6.11 MeV PGNAA Bone ashCa 40 Ca(n, ) 41 Ca E =6.42 MeV PGNAA Intra-cellular spaceK 40 K natural radioactivity E =1.46 MeV WBC Total Water-- 2 H 2 0 or 3 H 2 0 dilution Muscle mass*P 31 P(n, a) 28 Al E =1.778 MeV, t 1/2 =2.3 m DGNAA at TANDEM Total body fatC 12 C(n, n ) 12 C E =4.43 MeV Inelastic scatter gamma ray analysis at TANDEM Total body OxygenO 16 O(n, n ) 16 O E =6.13 MeV Inelastic scatter gamma ray analysis at TANDEM
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LIBRA Kick-off meeting, March 11, 2009 Optimization Monte Carlo simulations for optimization of experimental setup Irradiation geometry Detector position and response Radiation shielding from O’Meara et al 2001
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LIBRA Kick-off meeting, March 11, 2009 Complementarities High thermal neutron fluxes (up to 10 14 cm -2 s -1 ) Large irradiation volumes (i.e. up to 0.2 l in-core or up to 5 l at the thermal neutron column) Exploitation of the thermal neutron capture reactions cross-sections Reactor Accelerator “Fast neutron” activation analysis ( 14 N(n,2n) 13 N, 31 P(n,a) 28 Al) Neutron inelastic scattering gamma analysis 12 C(n,n’γ) 12 C, 16 O(n,n’γ) 16 O Penetration of fast neutrons in materials for LSNAA
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LIBRA Kick-off meeting, March 11, 2009 Thank you for your attention!
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