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Nuclear Physics Institute, Academy of Sciences of Czech Republic Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague. Cross-sections of Neutron Threshold Reactions studied by activation method. Diploma Thesis
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Nuclear Physics Institute, Academy of Sciences of Czech Republic Department of Nuclear Reactors, Faculty of Nuclear Sciences andPhysical Engineering, Czech Technical University in Prague Cross-sections of Neutron Threshold Reactions studied by activation method Diploma Thesis Vrzalová Jitka Supervisor: RNDr. Vladimír Wagner, CSc.
Outline • - Motivation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion • Motivation • Nuclear data libraries • Stochastic and deterministic codes • Neutron sources • Cross-section measurements • Experiments on Cyclotron in Řež • TSL Uppsala experiments • Comparison • Conclusion
Motivation • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion • for testing of the programs simulating ADS, it is necessary to determine neutron fields • the neutron fields can be determined using the activation detectors • for neutron detection are used threshold reactions on Au, Al, Bi, In, Ta, Ni, Zn, Y, I • almost no experimental cross-section data for most of observed threshold reactions are available for higher neutron energies (E>20MeV)→it is necessary to perform new cross-section measurements
Evaluated nuclear data libraries x EXFOR • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion • nuclear data are summarized in the libraries of nuclear data and gradually updated • data form ENDF-6 • general libraries (BROND-russian, CENDL-chinese, ENDF-american, JEFF- european, JENDL-japanese) • specialized libraries (MENDL, WIND, LA 100, LA 150, NRG-2003) • cross-sections are for the major part of measured isotopes published up to (n,4n) reaction (100 MeV) in ENDF, in EXFOR up to 40 MeV
Stochastic codes • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion MCNP a MCNPX • MCNP simulates transport of neutrons (photons and electrons) in energy range from 10-11 MeV to 20 MeV • MCNPX-connects and improves possibilities of MCNP, which is intended for lower energies and code LAHET, which is advisable for simulation of spallation reaction LAHET • simulates spallation reaction and transport nucleons, pions, muons with energy E≥20 MeV More Monte Carlo-based codes: FLUKA, HETC, NUCLEUS, SHIELD, NMTC, GEM, JAM
Deterministic codes • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion TALYS 1.0 • deterministic code • provides complete calculation of the nuclear reactions in the energy range from 1 keV to 200 MeV • with TALYS code can be obtained the complete overview of cross-sections • the output file contains all usually demanded information, more than 200 keywords could be used in the input file More codes: GNASH, ALICE, STAPRE, EMPIRE, MEND
TALYS 1.0 – nuclear models • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion
TALYS 1.0 – nuclear models Difference between cross-sections models with different nuclear level density and default Fermi model, reaction 209Bi(n,3n)207Bi • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion
Ta Al Au Bi Co In Detection of neutrons • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion
Evaluation • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion • decay during cooling, irradiation • unstable irradiation • coincidences • non point-like emitters • detector dead time • detector efficiency • self-absorption
Cross-sectionmeasurements • Requirements for s-measurements by activation method: • high energy neutron source with good intensity • monoenergetic (quasi-monoenergetic) neutrons or well known spectrum • pure monoisotopic samples • good spectroscopic equipment – g and X-rays detectors • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion Then we can calculate Nyield and finally : Number of neutrons in peak Evaluation process: Irradiation→HPGe→Deimos→Corrections→Yield→Cross-section
Neutron sources • source with wide spectrum of neutrons-time of flight method-determination energy of neutrons (system n_TOF in CERN), unsuitable for activation foils • quasi-monoenergetic neutron source - target + accelerator of particles - high-frequency source 7Li(p,n)7Be, 2H(d,n)3He • source CYRIC with energy range from 40 to 90 MeV in „Cyclotron and Radioisotope Center“ in Tohok • new source SPIRAL-2 is under construction in laboratory GANIL in Caen (France) (energy range to 40 MeV, high intensity) • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion
Neutron sources • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion Blue Hall, Uppsala Quasi-monoenergetic neutron source Neutron source on cyclotron U-120M
Experiments in Řež • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion • April, May 2009, irradiation of the foils on cyclotron U-120M • quasi-monoenergetic neutron source based on reaction 7Li(p,n)7Be, energy range of this neutron source is 10-37 MeV • proton beam energies 32.5 and 37 MeV • irradiation time about 20 h.,irradiated foils: Ni, Zn, Bi, Cu, In, Al, Au, Ta, Fe and I
Experiments in Řež • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion
Experiments in Uppsala • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion • February 2010, June 2008 • quasi-monoenergetic neutron source based on reaction 7Li(p,n)7Be, energy range of this neutron source is 11-175 MeV • proton beam energies 25, 50, 100 MeV (June 2008); 62, 70, 80, and 93 MeV(February 2010) • irradiation time about 8 h.,irradiated foils: Au, Bi, In, Al, Ta, Co, Y and I
Experiments in Uppsala HPGe detector • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion placing samples toward detector samples for irradiation
Comparison Řež, Uppsala Comparison of cross-section reaction (n,2n) 197Au with EXFOR and TALYS • Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion Řež Řež Uppsala Uppsala
Comparison Řež, Uppsala Comparison of cross-section reaction (n,xn) natIn with EXFOR and TALYS • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion Řež Řež Uppsala Uppsala Uppsala
Comparison Řež, Uppsala Comparison of cross-section reaction (n,2n) 64Zn with EXFOR and TALYS • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion Řež Řež Uppsala Uppsala
Conclusion • - Motivation • Introduction • Libraries • Stochastic and • deterministic • codes • Detection of • neutrons • Evaluation • - Cross - section • measurements • - Neutron sources • -Experiments-Řež • - Experiments- • Uppsala • - Comparison • Řež, Uppsala • - Conclusion • Our cross-section measurements in Uppsala and Řež coverwide spectrum of energies • Our results for well known cross-sections agree with other experimental data • We measured also a lot of new experimental data • Near future: publish the measured cross-sections from Uppsala at February 2010 Thanks for attention