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Studies of neutron cross-sections by activation method in Nuclear Physics Institute Řež and in The Svedberg Laboratory Uppsala and experimental determination.

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Presentation on theme: "Studies of neutron cross-sections by activation method in Nuclear Physics Institute Řež and in The Svedberg Laboratory Uppsala and experimental determination."— Presentation transcript:

1 Studies of neutron cross-sections by activation method in Nuclear Physics Institute Řež and in The Svedberg Laboratory Uppsala and experimental determination of neutron production in spallation reactions Nuclear Physics Institute, Academy of Sciences of the Czech Republic Dzelepov Laboratory of Nuclear Problems, Joint Institute for Nuclear Research, Russia Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague Varna, Bulgaria 16.-22.9.2013 J. Vrzalová, O. Svoboda, A. Kugler, M. Suchopár, V. Wagner collaboration Energy and Transmutation of Radioactive Waste vrzalova@ujf.cas.cz

2 2 Introduction  The collaboration Energy and Transmutation of Radioactive Waste use different setups consisting of lead, natural uranium and graphite irradiated by relativistic protons and deuterons to study transmutation of radioactive materials by produced neutrons.  Activation samples are used to determine production of neutron flux in different places of experimental set- ups.  Unfortunately, the cross-sections of many reactions important for our activation detectors are missing.  To improve situation, we studied the neutron cross- sections using different quasi-monoenergetic neutron sources based on proton reaction on 7 Li target in NPI Řež and in The Svedberg Laboratory Uppsala. - Motivation - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion

3 3 Outline - Motivation - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion  Motivation  Cross-section measurements  Neutron sources in NPI and TSL  Background subtraction  Experiments on cyclotron in Řež  TSL Uppsala experiments  Comparison  Conclusion

4 4 Motivation - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion  we measured threshold reactions on Au, Al, Bi, In, Ta, Ti, Y commonly used for such purposes and we also studied other materials: Cu, Fe, I, Mg, Ni, Zn. evaluated from the experiment we would like to find! poor knowledge, we want to measure Solving a Fredholm equation we can find Φ(E):  the spatial distribution of neutron field inside ADS-setup can be determined with the help of Fredholm equation  due to poor knowledge for us imported neutron cross- section we carried out series of experiments devoted to their determination

5 5 Evaluation process -Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion BACKGROUNDSUBTRACTION

6 6 Spectroscopic corrections - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Self-absorption Detector efficiency Correction for real coincidences Square-emitter corection Dead time correction Decay during cooling Decay during irradiation Unstable irradiation  Uncertainty caused by the corrections was estimated to be less than 1% in total, except the uncertainty from efficiency calibration of the detector, which is below 3 %.

7 7 Evaluation - total yield - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Peak areaSelf-absorption correction Beam correction Dead time correction Decay during cooling and measurement γ line intensity Detector efficiency Correction for coincidences Square-emitter correction Weight normalization Decay during irradiation

8 8 Cross-section measurements - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Requirements for  -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 –  and X-rays detectors Then we can calculate N yield and finally : Number of neutrons in peak foil sizerelative mass Avogadro´s number

9 9 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, Uppsala - Conclusion Neutron sources NPI ASCR Řež: Energy range 14 – 37 MeV, neutron intensity ~ 10 8 n.cm -2.s -1 TSL Uppsala: Energy range 20 – 180 MeV, neutron intensity ~ 10 5 n.cm -2. s -1 Neutron spectra comparison

10 10 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Background subtraction background contribution was determined by folding of the neutron source spectrum and calculated cross-sections (TALYS 1.4) we calculated ratio between production in neutron peak and total production and with this ratio we multiplied the yields to subtract background production

11 11 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Uncertainty analysis  HPGe detector calibration uncertainty: less than 3%  Gauss-fit of the gamma peaks: > 1% (usually less than 10%)  spectroscopic corrections uncertainty: less than 1%  neutron spectra determination: 10%  neutron beam intensity determination: 10%  uncertainty of background subtraction: 10% in the worst case (big background, big model influence)

12 12 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Experiments in NPI  four measurements  proton beam energies 20, 25, 32.5 and 37 MeV  irradiation time about 20 h.,irradiated foils: Ni, Zn, Bi, Cu, In, Al, Au, Ta, Fe and I  the sample distances from the lithium target – from 11 cm to 16 cm

13 13 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Experiments in TSL  proton beam energies 50, 62, 70, 80, and 92 and 97 MeV  irradiation time about 8 h

14 14 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion NPI and TSL results Comparison of cross-sections (n,xn) reactions on natural indium with TALYS

15 15 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Comparison of cross-sections (n,xn) reactions on iodine and tantalum with EXFOR, TALYS and libraries of evaluated data

16 16 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Comparison of cross-sections (n,x) reactions on aluminium and yttrium with TALYS, EXFOR and libraries of evaluated data

17 17 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Also with the help of our measured cross-section we can analyze neutron flux in different places of experimental set-ups consisting of lead, natural uranium and graphite irradiated by relativistic protons and deuterons (for example QUINTA – more about this setup in the talk of Mr. Furman or Mr. Wagner). - neutron flux determined with the help of method “effective cross- sections” (experiment at phasotron in JINR Dubna – 660MeV protons, massive lead target, threshold detectors were situated on the target surface).

18 18 - Motivation Evaluation Corrections - Cross - section measurements - Neutron sources - Background subtraction - NPI Řež - TSL Uppsala - Comparison NPI, TSL - Conclusion Conclusion  ten cross-section measurements were carried out in NPI Řež and in TSL Uppsala  energy region from 17 MeV to 94 MeV was covered  we studied various materials in the form of thin foils and observed good agreement with the data in EXFOR database and also with the cross- sections calculated in deterministic code TALYS.  with the help of neutron cross-section we can analyze neutron flux in different places of experimental set-ups  all our observed reactions you can find in journal: Nuclear Instruments and Methods in Physics Research - Vol.726, (2013) 84-90  some of our results are already included in EFXOR

19 19 Thank you! supervisor in NPI Řež: RNDr. Vladimír Wagner, CSc. supervisor in JINR Dubna: prom. fyz. Jindřich Adam, CSc. wagner@ujf.cas.cz iadam@jinr.ru

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