at TSL high energy neutron facility

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Presentation transcript:

at TSL high energy neutron facility 25th HNPS, 3-4 June 2016 197Au(n,xn) reactions at TSL high energy neutron facility at Uppsala NATIONAL TECHNICAL UNIVERSITY OF ATHENS UPPSALA UNIVERSITET Antigoni Kalamara

Motivation Studies of excitation functions of nuclear reactions are of considerable importance for testing nuclear models as well as for practical applications. Neutron induced reactions on 197Au are used as reference reactions thus it is very important to have complete and reliable data. The residual nuclei from the 197Au(n,xn) channels have reasonable half-lives and can be measured using the activation method, providing a complete set of exit channels for testing nuclear models. Above 20 MeV, existing data for the (n,3n) and (n,4n) reactions were obtained with very poor statistics and present many discrepancies among them, while for the (n,5n) and (n,6n) channels, only few data points exist. Above 20 MeV a truly monoenergetic neutron beam is not feasible in a strict sense. However, for certain nuclear reactions there is a strong dominance of neutrons in a narrow energy range and such neutron sources are often called “quasi-monoenergetic”. Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

The interaction n + 197Au 197Au (n,2n) 196Au Τ1/2 = 6.2 h Τ1/2 = 186.1 d 197Au (n,4n) 194Au Τ1/2 = 38.0 h 197Au (n,5n) 193Au Τ1/2 = 17.7 h 197Au (n,6n) 192Au Τ1/2 = 3.2 h 197Au (n,7n) 191Au Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

TSL  The Svedberg Laboratory The interaction n + 197Au 197Au (n,2n) 196Au Τ1/2 = 6.2 h 197Au (n,3n) 195Au Τ1/2 = 186.1 d 197Au (n,4n) 194Au Τ1/2 = 38.0 h 197Au (n,5n) 193Au Τ1/2 = 17.7 h 197Au (n,6n) 192Au Τ1/2 = 3.2 h 197Au (n,7n) 191Au The most popular reaction for the production of a quasi-monoenergetic neutron beam above 20 MeV is 7Li(p,n)7Be. TSL  The Svedberg Laboratory (Uppsala) Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

The interaction n + 197Au In order to determine the cross section of the (n,xn) reactions, the neutron energy distribution is needed, thus the characterization of the beam is of major importance. 197Au (n,2n) 196Au Τ1/2 = 6.2 h 197Au (n,3n) 195Au Τ1/2 = 186.1 d 197Au (n,4n) 194Au Τ1/2 = 38.0 h 197Au (n,5n) 193Au Τ1/2 = 17.7 h 197Au (n,6n) 192Au Τ1/2 = 3.2 h 197Au (n,7n) 191Au The most popular reaction for the production of a quasi-monoenergetic neutron beam above 20 MeV is 7Li(p,n)7Be. A Gustaf Werner cyclotron is used for neutron production through: beam 𝑯 𝟐 + ions with energy of ~13 MeV A-1 proton beam with energy variable in the 25-180 MeV range. The energy of the produced peak neutrons is controllable in the 11-175 MeV range. THE TSL NEUTRON BEAM FACILITY, Radiation Protection Dosimetry (2007), Vol. 126, No. 1–4, pp. 18–22, doi:10.1093 Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Experimental setup at TSL CUP → Close User Position (~2 m) Overview of the irradiation lab. SUP → Standard User Position (~4 m) CUP CUP p+7Li n p SUP CUP SUP ToF measurements Thin Film Breakdown Counters Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Activation Measurements Following the irradiations, the induced activity on the samples was measured with a high-purity germanium (HPGe) detector of 80% relative efficiency, properly shielded with lead blocks in order to reduce the contribution of the natural radioactivity. 10 cm The samples were placed at a distance of 10 cm from the detector window so that the corrections for coincidence summing become negligible. The detectors were calibrated using 152Eu, 133Ba and 137Cs sources. Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Spectra Investigation 197Au(n,4n)194Au 197Au(n,5n)193Au 255.6 keV 948.3 keV 197Au(n,6n)192Au 197Au(n,7n)191Au T1/2 = 38 h T1/2 = 18 h 316.5 keV 586.5 keV Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

MCNP5 Simulations In order to study the neutron beam profile, MCNP5 simulations were performed taking into account the experimental set up in high detail. 3D-View CUP SUP Au foil at SUP position Foils at CUP position Proton beam dump tube Fe wall The whole magnet Li target Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Lateral homogeneity within 3%. MCNP5 Simulations MCNP5 Results In order to study the neutron beam profile, MCNP5 simulations were performed taking into account the experimental set up in high detail. The surrounding materials contribute to a low energy neutron tail which is not essential when studying threshold reactions. CUP Lateral homogeneity within 3%. Neutron energy distribution Check: Lateral homogeneity of neutron flux on the target set up. The effects of surrounding materials to the neutron flux. Concrete floor, ceiling and walls Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Estimation of the absolute neutron flux 𝑅𝑅 𝑚𝑐𝑛𝑝 = 𝑖=0 𝑀𝑒𝑉 70 𝑀𝑒𝑉 𝜎 𝑖 𝐸 ∙ 𝛷 𝑚𝑐𝑛𝑝 𝑖 (𝛦) The reaction rate can be determined theoretically according to this expres-sion: Εi 𝑅𝑅 𝑚𝑐𝑛𝑝 = 𝑖=0 𝑀𝑒𝑉 70 𝑀𝑒𝑉 𝜎 𝑖 𝐸 𝑖 ∙ 𝛷 𝑚𝑐𝑛𝑝 𝑖 ( 𝐸 𝑖 The cross section of the reaction is determined by interpolating the TENDL data. The neutron flux in the target is taken from simulation. Moreover, the reaction rate can be defined experimentally with this expression: Decay constant of the residual nucleus. 𝑅𝑅 𝑒𝑥𝑝𝑒𝑟𝑖𝑚𝑒𝑛𝑡𝑎𝑙 ( 𝑠𝑒𝑐 −1 )= 𝜆 ∙ 𝑁 𝑝 𝑁 𝑡 Number of the produced nuclei. Number of the target nuclei. Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Estimation of the absolute neutron flux 𝑟 ( 𝑠𝑒𝑐 −1 )= 𝑅𝑅 𝑒𝑥𝑝𝑒𝑟𝑖𝑚𝑒𝑛𝑡𝑎𝑙 𝑅𝑅 𝑚𝑐𝑛𝑝 After finding the normalization factor r: 𝑅𝑅 𝑚𝑐𝑛𝑝 = 𝑖=0 𝑀𝑒𝑉 70 𝑀𝑒𝑉 𝜎 𝑖 𝐸 𝑖 ∙ 𝛷 𝑚𝑐𝑛𝑝 𝑖 ( 𝐸 𝑖 𝑟 ( 𝑠𝑒𝑐 −1 )= 𝑅𝑅 𝑒𝑥𝑝𝑒𝑟𝑖𝑚𝑒𝑛𝑡𝑎𝑙 𝑅𝑅 𝑚𝑐𝑛𝑝 𝑅𝑅 𝑒𝑥𝑝𝑒𝑟𝑖𝑚𝑒𝑛𝑡𝑎𝑙 ( 𝑠𝑒𝑐 −1 )= 𝜆 ∙ 𝑁 𝑝 𝑁 𝑡 The total absolute neutron flux can be estimated through the expression: 𝑇𝑜𝑡𝑎𝑙 𝑁𝑒𝑢𝑡𝑟𝑜𝑛 𝐹𝑙𝑢𝑥 𝑛 𝑐𝑚 2 𝑠𝑒𝑐 = 𝑖=0 𝑀𝑒𝑉 70 𝑀𝑒𝑉 𝑟 ∙ 𝛷 𝑚𝑐𝑛𝑝 𝑖 ( 𝐸 𝑖 8.4 x 104 n/cm2 s Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Future work To normalize the absolute value of the neutron spectrum and testify the results with well known reference reactions: 27Al(n,a) 93Nb(n,2n) 238U(n,f) To deduce the cross section of (n,4n), (n,5n) (n,6n) and (n,7n) reactions. Theoretical calculations using the EMPIRE code. The most accurate information about the neutron flux distribution will be provided from the ToF spectrum. Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

25th HNPS, 3-4 June 2016 Future work To normalize the absolute value of the neutron spectrum and testify the results with well known reference reactions: 27Al(n,a) 93Nb(n,2n) 238U(n,f) To deduce the cross section of (n,4n), (n,5n) (n,6n) and (n,7n) reactions. Theoretical calculations using the EMPIRE code. The most accurate information about the neutron flux distribution will be provided from the ToF spectrum. A. Kalamara, R. Vlastou, M. Kokkoris, A. Stamatopoulos, A. Mattera, M. Lantz, E. Passoth, A. Prokoviev and V. Rakopoulos Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

25th HNPS, 3-4 June 2016 Future work To normalize the absolute value of the neutron spectrum and testify the results with well known reference reactions: 27Al(n,a) 93Nb(n,2n) 238U(n,f) To deduce the cross section of (n,4n), (n,5n) (n,6n) and (n,7n) reactions. Theoretical calculations using the EMPIRE code. The most accurate information about the neutron flux distribution will be provided from the ToF spectrum. A. Kalamara, R. Vlastou, M. Kokkoris, A. Stamatopoulos, A. Mattera, M. Lantz, E. Passoth, A. Prokoviev and V. Rakopoulos

25th HNPS, 3-4 June 2016 Future work To normalize the absolute value of the neutron spectrum and testify the results with well known reference reactions: 27Al(n,a) 93Nb(n,2n) 238U(n,f) To deduce the cross section of (n,4n), (n,5n) (n,6n) and (n,7n) reactions. Theoretical calculations using the EMPIRE code. The most accurate information about the neutron flux distribution will be provided from the ToF spectrum. A. Kalamara, R. Vlastou, M. Kokkoris, A. Stamatopoulos, A. Mattera, M. Lantz, E. Passoth, A. Prokoviev and V. Rakopoulos

TFBC’s Stop signal! TFBC  Thin Film Breakdown Counter j Stop signal! TFBC  Thin Film Breakdown Counter Fissionable Target 238U 238U(n,f) reaction Fission product HV Two electrodes separated by a dielectric layer Breakdown discharge The electric field between the two electrodes is sufficient to induce a breakdown once a fission product creates free charges in the dielectric layer. The current generated produces a detectable signal and at the same time evaporates a portion of the electrode, interrupting the short-circuit. Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016

Different neutron beam apertures j Antigoni Kalamara, NTUA 25th ΗΝPS, June 2016