Measurement of Cross-sections of Yttrium (n,xn) Threshold Reactions by Means of Gamma Spectroscopy (original) (raw)
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Measurement of cross-sections for 89Y(n,xn) reaction at average neutron energies of 15–36 MeV
Journal of Radioanalytical and Nuclear Chemistry, 2014
We measured neutron-induced reaction crosssections for 89 Y(n,2n) 88 Y, 89 Y(n,3n) 87 Y, and 89 Y(n,4n) 86 Y reactions with the average neutron energy region from 15.9 to 36.3 MeV by using an activation and off-line c-ray spectrometric technique. High energy neutrons were produced from the 9 Be(p,n) reaction with 25-, 35-and 45-MeV proton beam from the MC-50 Cyclotron at Korea Institute of Radiological and Medical Sciences (KIRAMS). The neutron-induced reaction cross-sections of 89 Y as a function of neutron energy were calculated using the TALYS 1.6. The flux-weighted average cross-sections for 89 Y(n,xn; x = 2-4) reactions are also calculated from the TALYS values based on mono-energetic neutron and by using the neutron spectrum from MCNPX 2.6.0 code. The present results for 89 Y(n,xn; x = 2-4) reactions are compared with the flux-weighted values of TALYS and are found to be in good agreement.
Measurement of reaction cross-sections for 89 Y at average neutron energies of 7.24-24.83 MeV
EPJ Web of Conferences, 2015
We measured neutron-induced reaction cross-sections for 89 Y(n,γ) 90m Y and 89 Y(n,α) 86 Rb reactions with the average neutron energy region from 7.45 to 24.83 MeV by an activation and off-line γ-ray spectrometric technique using the MC-50 Cyclotron at Korea Institute of Radiological and Medical Sciences. The neutron-induced reaction cross-sections of 89 Y as a function of neutron energy were taken from the TENDL-2013 library. The flux-weighted average cross-sections for 89 Y(n,γ) 90m Y and 89 Y(n,α) 86 Rb reactions were calculated from the TENDL-2013 values based on mono-energetic neutron and by using the neutron energy spectrum from MCNPX 2.6.0 code. The present results are compared with the flux-weighted values of TENDL-2013 and are found to be in good agreement
Measurements of 89Y(n,2n)88Y and 89Y(n,3n)87Y, 87mY cross sections for fast neutrons at KIRAMS
EPJ Web of Conferences, 2017
A proton cyclotron MC-50 in Korea Institute of Radiological & Medical Science (KIRAMS) is used to carry out neutron activation experiments with Y 2 O 3 targets irradiated with neutron beams of a continuous spectrum produced by proton beams on a thick beryllium target. Neutrons are generated by 9 Be (p, n) reaction with an incident proton intensity of 20 µA. The neutron spectra generated by proton beams of 30, 35, and 40 MeV are calculated by GEANT4 simulations. Nb powders are used for neutron flux monitoring by measuring the activities of 92m Nb through the reaction 93 Nb (n, 2n). By using a subtraction method, the average cross section of 89 Y(n,2n) and 89 Y(n,3n) reactions at the neutron energies of 29.8 ± 1.8 MeV and 34.8 ± 1.8 MeV are extracted and are found to be close to the existing cross sections from the EXFOR data and the evaluated nuclear data libraries such as TENDL-2015 or EAF-2010.
Yttrium as a New Threshold Detector for Fast Neutron Energy Spectrum (>10 MeV) Measurement
Journal of the Korean Physical Society, 2011
Results of two experiments with Yttrium 89 probe are presented. The experiment assembly (U/Pb model) was irradiated with Dubna NUCLOTRON for 1.6 and 2.52 GeV deuteron beam and we obtain Neutron Energy Spectrum inside whole 3D model by using threshold energy reaction. Normally in experiment like this one uses neutron activation detectors made from gold (197 Au), cobalt (59 Co), bismuth (209 Bi) etc. Detector, yttrium (89 Y) was proposed. Yttrium detectors give quite good results for neutron energy spectrum from 10 MeV to about 50 MeV
Journal of Radioanalytical and Nuclear Chemistry, 2019
The 67 Zn(n,p) 67 Cu, 64 Zn(n,2n) 63 Zn, 89 Y(n,γ) 90m Y and 89 Y(n,2n) 88 Y reaction cross sections relative to the 197 Au(n,2n) 196 Au monitor reaction have been determined at the neutron energy of 14.54 ± 0.002 MeV by using the method of activation and off-line γ-ray spectrometry. The neutron energy used was obtained from the 3 H(d,n) 4 He reaction. The covariance analysis was performed by taking the uncertainties arising in various attributes and the correlations between those attributes. The analyzed results from the present measurement were compared with the literature data and evaluated data of various libraries like ENDF/B-VIII, JEFF-3.3, JENDL-4.0 and ROSFOND-2010 libraries as well as with the calculated values based on TALYS-1.9 code. Keywords 67 Zn(n,p) 67 Cu • 64 Zn(n,2n) 63 Zn, 89 Y(n,γ) 90m Y and 89 Y(n,2n) 88 Y reactions • 3 H(d,n) 4 He reaction neutron • γ-Ray spectrometry • Covariance analysis • TALYS-1.9
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2012
Production cross-sections of the 89 Y(p,x) 86,88,89g Zr, 86m+g,87g,87m,88g Y, 85g Sr, and 84g Rb nuclear processes were investigated up to 42-MeV proton energy by using a stacked-foil activation technique at the MC-50 cyclotron of the Korea Institute of Radiological and Medical Sciences. Cumulative cross-sections of the 88g Y radionuclide have been reported here for the first time from proton activation on natural yttrium target. The present data were compared with the available experimental data as well as theoretical calculations based on the TALYS and the ALICE-IPPE codes, and found in general good agreement among them. Due to the mono-isotopic characteristics of the natural yttrium, the investigated 89 Y(p,x) 86,88,89g Zr, 86m+g,87g,87m,88g Y, 85g Sr, and 84g Rb processes are suitable for testing of nuclear reaction theories and/or mechanism. A quantitative analysis has also done to understand more accurately the predictive power of the model codes by performing calculations of deviation factors between the measured data and respective model calculations. The thick target integral yields, i.e., induced radioactivity per unit fluence of 42-MeV protons were also deduced from the measured cross-sections of the investigated radionuclides. Optimal production pathway for the 89 Zr-PET radionuclide using a cyclotron is discussed elaborately. The measured cross-sections of 87g Y, 88g Y, 88 Zr, and 89g Zr radionuclides find importance due to their suitable decay characteristics leading to medical and thin layer activation applications. In addition, the present experimental results will play an important role in enrichment of the literature data base for proton-induced reactions on natural yttrium leading to various applications.
Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine, 2014
In this study, the activation cross sections were measured for (142)Nd(n,α)(139m)Ce reaction at four neutron energies between 13.57 and 14.83 MeV, which were produced by a neutron generator through (3)H((2)H,n)(4)He reaction. The production of short-lived activity and the spectra accumulation were performed by the cyclic activation technique. Induced gamma-ray activities were measured using a high resolution gamma ray spectrometer equipped with a high-purity Germanium (HpGe) detector. In the cross section measurements, corrections were made regarding the effects of the gamma-ray attenuation, the dead-time, the fluctuation of the neutron flux, and low energy neutrons. The measured cross sections were compared with the published literature and the results of the model calculation (TALYS 1.4).
Absolute measurements of fast neutrons using yttrium
Review of Scientific Instruments, 2010
Yttrium is presented as an absolute neutron detector for pulsed neutron sources. It has high sensitivity for detecting fast neutrons. Yttrium has the property of generating a monoenergetic secondary radiation in the form of a 909 keV gamma-ray caused by inelastic neutron interaction. It was calibrated numerically using MCNPX and does not need periodic recalibration. The total yttrium efficiency for detecting 2.45 MeV neutrons was determined to be f n ϳ 4.1ϫ 10 −4 with an uncertainty of about 0.27%. The yttrium detector was employed in the NX2 plasma focus experiments and showed the neutron yield of the order of 10 8 neutrons per discharge.