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Journal articles on the topic 'Neutron activation method'

Author: Grafiati

Published: 5 June 2025

Last updated: 15 July 2025

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1

Namakonov, V., S. Andreyev, D. Gabbasov, A. Moseyeva, and D. Sergina. "MEASUREMENT OF 14 MEV NEUTRONS TRANSMISSION THROUGH LITHIUM HYDRIDE LAYERS WITH TIME-OF-FLIGHT METHOD." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2020, no. 4 (2020): 33–39. http://dx.doi.org/10.55176/2414-1038-2020-4-33-39.

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The results of experiments on transmission of 14 MeV neutrons through lithium hydride layers of thickness up to 25 cm are presented in the article. The measurements were performed with time-of-flight method on a pulse channel of neutron generator NG-12I. The operating mode of the neutron generator is pulse-periodic. Neutrons passing through the layers of Li hydrides were registered by detector based on a 70×70 mm stilbene crystal scintillator. NIM standard modules were used as measuring equipment. The neutron yield from the generator target was estimated by neutron monitor with a fluorine plas

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2

UEMINO, YOSHITOMO. "Neutron Spectrometry with Activation Method." RADIOISOTOPES 46, no. 9 (1997): 699–701. http://dx.doi.org/10.3769/radioisotopes.46.699.

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3

Mangan, M. A., C. L. Ruiz, G. W. Cooper, G. A. Chandler, and D. J. Ampleford. "Inferring neutron yields using indium activation samples for small fractions of tritium added to deuterium fuel in inertial confinement fusion (ICF) experiments." Review of Scientific Instruments 93, no. 10 (2022): 103514. http://dx.doi.org/10.1063/5.0101823.

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In inertial confinement fusion experiments, the neutron yield is an important metric for thermonuclear fusion performance. Neutron activation diagnostics can be used to infer neutron yields. The material used for neutron activation diagnostic undergoes a threshold reaction so that only neutrons having energies above the threshold energy are observed. For thermonuclear experiments using deuterium (D) and tritium (T) fuel constituents, neutrons arising from D + D reactions (DD-neutrons) and neutrons resulting from D + T reactions (DT-neutrons) are of primary interest. Indium has two neutron acti

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4

Reyhancan, Iskender Atilla. "Measurements of activation cross sections by cyclic activation method for (n,2n) reaction on 144Sm isotope around 14 MeV neutron energy." Radiochimica Acta 107, no. 1 (2018): 33–37. http://dx.doi.org/10.1515/ract-2018-2983.

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Abstract Measurement of activation cross sections for the 144Sm(n,2n)143gSm reaction was performed by Cyclic Activation Method (CAM) around 14 MeV neutron energy. Natural samarium samples were irradiated by the neutrons produced by 3H(2H,n)4He reaction using a neutron generator. Delayed γ ray activities produced by fast neutrons in samples were measured by a high resolution γ ray spectrometer [high-purity Germanium (HpGe) detector]. The measured cross sections are compared with the results of model calculation (STAPRE code) and evaluated data (JEFF 3.0/A).

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5

Ivannikov, Sergei, Nikita Markin, and Veniamin Zheleznov. "Determination of uranium in solutions by the neutron activation analysis method with 252Cf radionuclide neutron source." Nuclear Technology and Radiation Protection 36, no. 1 (2021): 12–17. http://dx.doi.org/10.2298/ntrp201217005i.

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A determination option for 238U in solutions by the neutron activation analysis was investigated. A radionuclide treatment based on 252Cf was used as a neutron source. The limit for the determination of uranium using thermal neutrons of 0.1 mgL?1 was determined within the research framework. With the help of the preliminary concentration of the sample via the evaporation method, it is possible to further reduce the detection limit by 2-5 times. It is defined that the optimal time for measuring the induced activity of the sample when working with a short-life isotope of 239U, is 30 minutes. The

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6

Begun, S. V., N. R. Dzysiuk, I. M. Kadenko, V. K. Maidanyuk, and G. I. Primenko. "Cross sections of (n, p) nuclear reactions on zirconium isotopes." Nuclear Physics and Atomic Energy 8, no. 3 (2007): 42–46. https://doi.org/10.15407/jnpae2007.03.042.

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Cross sections of nuclear reactions 92Zr(n, p)92Y and 94Zr(n, p)94Y were measured in the neutron energy range 13.56 ÷ 14.53 MeV. Measurements have been carried out by neutron activation method. The samples in the form of foils of natural zirconium have been irradiated by DT- neutrons. Instrumental gamma-spectra of activation products have been measured by spectrometer with HPGe detector. The corrections on the instability of neutron flux, real geometry of the experiment, the effect of true coincidence summing of gamma-quanta during activation products spectra measurements and on effect of abso

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7

Salama, Tarek Mohamed Talaat, N. A. Mansour, and M. Fayez-Hassan. "Neutron Activation Analysis of Some Building Material." JOURNAL OF ADVANCES IN PHYSICS 14, no. 2 (2018): 5564–73. http://dx.doi.org/10.24297/jap.v14i2.7507.

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Neutron activation analysis (NAA), based on the comparator method, has the potential to fulfill the requirements of a primary ratio method as defined in 1998 by the Comité Consultatif pour la Quantité de Matière — Métrologie en Chimie (CCQM, Consultative Committee on Amount of Substance — Metrology in Chemistry Studies of Neutron Activation Analysis (NAA) have been carried out on different Egyptian building material samples. The technique of neutron activation analysis is based on the measurement of radiation released by the decay of radioactive nuclei formed by neutron irradiation of the mate

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8

Laszynska, Ewa, Slawomir Jednorog, Adam Ziolkowski, Michal Gierlik, and Jacek Rzadkiewicz. "Determination of the emission rate for the 14 MeV neutron generator with the use of radio-yttrium." Nukleonika 60, no. 2 (2015): 319–22. http://dx.doi.org/10.1515/nuka-2015-0040.

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Abstract The neutron emission rate is a crucial parameter for most of the radiation sources that emit neutrons. In the case of large fusion devices the determination of this parameter is necessary for a proper assessment of the power release and the prediction for the neutron budget. The 14 MeV neutron generator will be used for calibration of neutron diagnostics at JET and ITER facilities. The stability of the neutron generator working parameters like emission and angular homogeneity affects the accuracy of calibration other neutron diagnostics. The aim of our experiment was to confirm the us

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9

Kilim, S., E. Strugalska-Gola, M. Szuta, et al. "Am-241 incineration measurements with activation method in the QUINTA neutron field." EPJ Web of Conferences 204 (2019): 04004. http://dx.doi.org/10.1051/epjconf/201920404004.

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Am-241 sample was irradiated in spallation neutrons produced in ADS setup QUINTA at the JINR in Dubna. The energy was 660 MeV in the proton beam. The incineration study method was based on gamma-ray spectrometry. During the analysis of the spectra, several fission products were identified. Fission product activities yielded the number of fissions. Nevertheless, the lines are assumed to belong to the neutron capture product covered by parasitic Np-238 decay lines. The Np-238 lines as a result of neutron capture by Np-237 made impossible to determine the number of captures in Am-241.

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10

Dzysiuk, N. R., I. M. Kadenko, V. K. Maydanyuk, G. I. Primenko, and A. M. Berlizov. "Determination of cross sections for nuclear reactions (n, x) at germanium isotopes." Nuclear Physics and Atomic Energy 8, no. 4 (2007): 68–71. https://doi.org/10.15407/jnpae2007.04.068.

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The cross section values for nuclear reactions 74Ge(n, α)71mZn, 70Ge(n, p)70Ga, 76Ge(n,2n)75mGe, 70Ge(n,2n)69Ge have been measured for neutron energy 14.53 MeV, and of reaction 72Ge(n, 2n)71Ge for energies 13.32, 13.69, 14.35, 14.74 MeV as well. Measurements have been carried out with neutron activation method. The samples in the form of disks of natural germanium have been irradiated with DT-neutrons. Instrumental gamma-spectra of activation products have been measured with two HPGe spectrometers. The corrections for neutron flux instability, real geometry of the experiment, the effect of gam

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11

Nguyen, Son An, Tien Van Dang, Thang Huu Ho, and Hieu Bao Quoc Phan. "Determination of the neutron beam diameter based on the neutron activation analysis." Science and Technology Development Journal 19, no. 4 (2016): 147–53. http://dx.doi.org/10.32508/stdj.v19i4.604.

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Neutron beam diameter is a very important parameter in the experimental nuclear research. Determination of the correct neutron beam diameter is the best method to prepare corectly the optimal sample size correctly, reduced data analysis errors. To measure the neutron diameter, some methods were used: Simulation by Monte – Carlo method, neutron image, and neutron activation analysis. In this report, we determined the neutron beam diameter of the 3rd horizontal channel of the Dalat nuclear reactor that activated gold foils. The result shows that this method offer quick and more correct results t

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12

Yashima, H., S. Sekimoto, T. Utsunomiya, et al. "Measurements of the neutron activation cross sections for Bi at 287 and 370 MeV." Proceedings in Radiochemistry 1, no. 1 (2011): 135–39. http://dx.doi.org/10.1524/rcpr.2011.0025.

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AbstractWe present cross section measurements for neutron-induced activation of Bi, at 287 and 370 MeV. These values were derived from the activation method using a quasi-monoenergetic neutron field based on the 7Li(p,n) reaction. In separate experiments, samples were irradiated with neutrons derived from 7Li(p,n) reaction at either 0º or 30º for proton beam axis. This approach allows the subtraction of the low energy neutron components. The measured cross sections are compared with the findings of other studies, and evaluated in relation to nuclear data files.

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13

Chatzakis, John, Iraklis Rigakis, Syed Hassan, Eugene Laurence Clark, Paul Lee, and Michael Tatarakis. "Design of a Pixelated Imaging System for Fast Neutron Sources." Designs 3, no. 2 (2019): 25. http://dx.doi.org/10.3390/designs3020025.

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Imaging detectors that use X-ray radiation and pulsed neutron sources have increased in sophistication in recent years due to the use of solid-state detectors. A key method for neutron detection is the nuclear activation of materials by neutrons. Neutron activation can generate radionuclides whose decay produces secondary particle emission that can be detected without interference from the X-rays and other prompt radiation sources and offers advantages over neutrons detection using scintillators. In this paper, we present the design of an imaging system for fast neutron sources. The imaging sy

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14

Greenberg, Robert R., Peter Bode, and Elisabete A. De Nadai Fernandes. "Neutron activation analysis: A primary method of measurement." Spectrochimica Acta Part B: Atomic Spectroscopy 66, no. 3-4 (2011): 193–241. http://dx.doi.org/10.1016/j.sab.2010.12.011.

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15

Király, B., and J. Csikai. "Investigations on thermal neutron reflection by activation method." Applied Radiation and Isotopes 52, no. 1 (2000): 93–96. http://dx.doi.org/10.1016/s0969-8043(99)00088-3.

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16

Zaghloul, R., E. Gantner, M. Mostafa, and H. J. Ache. "Epithermal neutron activation analysis using the monostandard method." Journal of Radioanalytical and Nuclear Chemistry Articles 109, no. 2 (1987): 295–307. http://dx.doi.org/10.1007/bf02037873.

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17

Perelli Cippo, E., C. Cazzaniga, M. Paoletti, et al. "Towards the use of SDD as an absolute detector for high-energy neutron measurements." Journal of Instrumentation 18, no. 05 (2023): C05019. http://dx.doi.org/10.1088/1748-0221/18/05/c05019.

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Abstract As of today, the standard method employed in tokamaks for the absolute measurement of the neutron flux (thus of the nuclear fusion power) is based on activation foils, being the most robust and unbiased technique for the absolute determination of neutron fluence. However, this technique is not able to provide real-time data useful for the control of future fusion plants like DEMO. In this paper, we present some preliminary results about the R&D activity aimed at developing the Single-crystal Diamond Detectors (SDD) used for fast neutron measurements into an absolute neutron flux m

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18

Enin, S., A. Belozerova, V. Pavlov, and T. Chernysheva. "NEUTRON-DOSIMETRIC SUPPORT OF CONSTRUCTION MATERIALS PROPERTIES RESEARCH EXPERIMENTS IN REACTOR CONDITIONS." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2020, no. 1 (2020): 154–62. http://dx.doi.org/10.55176/2414-1038-2020-1-154-162.

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JSC "SSC RIAR" has accumulated a rich experience in the neutron-dosimetric support and neutron fields spectrometry using the activation method. Through the efforts of a specialists group, this direction continues to evolve, with advanced developments and modern high-precision equipment. The development of unified standards, computational and experimental methods of neutron-dosimetric support/monitoring to establish a one-to-one accordance between the observed changes in the properties of reactor materials and the conditions of reactor irradiation is topical. The application and distribution of

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19

Kasilov, Valentin, Sergey Gokov, Sergiy Kalenik, et al. "Concept of Neutron Source Creation for Nuclear Medicine on the Basis of Linear Electron Accelerator." 4, no. 4 (December 10, 2021): 160–63. http://dx.doi.org/10.26565/2312-4334-2021-4-21.

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We review the current status of the development of sources of epithermal neutrons sources based on reactors and accelerators for boron neutron capture therapy (BNCT), a promising method of malignant tumor treatment. The scheme is proposed of the source prototype for the production of thermal and epithermal neutrons using the delayed neutrons generated with help of linear electron accelerator at the target containing the fissile material. The results of an experiment are presented in which the half-life curves of radioactive nuclei formed during fission and emitting delayed neutrons are measure

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20

Vasilopoulou, T., F. Tzika, and I. E. Stamatelatos. "Large Sample Neutron Activation Analysis: Developments and Perspectives." HNPS Proceedings 19 (January 1, 2020): 100. http://dx.doi.org/10.12681/hnps.2522.

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Most of the available analytical techniques do not comply with the need for direct trace element analysis of samples of mass exceeding the order of grams. Instead sub-sampling methods are used to obtain representative sampling of the studied material. Large Sample Neutron Activation Analysis (LSNAA) is a powerful technique, which can fulfill this need in a non-destructive way, free of sample size restrictions due to the high penetrating properties of neutrons and gamma rays in matter. However, corrections are required in order to obtain quantitative analysis results. Due to its distinct advant

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21

Mattsson, Hakan, and A. Nordlund. "EVALUATION OF THE PULSED NEUTRON ACTIVATION METHOD USING CFD." Journal of Flow Visualization and Image Processing 13, no. 3 (2006): 299–312. http://dx.doi.org/10.1615/jflowvisimageproc.v13.i3.60.

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22

Quartemont, Nicholas J., and James E. Bevins. "Regularized heuristic method for activation monitor neutron spectrum unfolding." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 1014 (October 2021): 165722. http://dx.doi.org/10.1016/j.nima.2021.165722.

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23

Usenko, P. L., V. V. Gaganov, and D. A. Molodtsev. "A Neutron Activation Method of Deuterium–Tritium Plasma Diagnostics." Plasma Physics Reports 46, no. 1 (2020): 29–34. http://dx.doi.org/10.1134/s1063780x20010171.

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24

Jovančević, N., L. Daraban, S. Oberstedt, et al. "Measurement of the Neutron Spectrum Using the Activation Method." Physics Procedia 59 (2014): 154–59. http://dx.doi.org/10.1016/j.phpro.2014.10.024.

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25

Stoeva, L., Ts Pantaleev, and A. Damyanova. "Neutron activation method for nitrogen determination in biological specimens." Journal of Radioanalytical and Nuclear Chemistry Articles 134, no. 2 (1989): 285–92. http://dx.doi.org/10.1007/bf02278265.

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26

Huang, Chun-Kai, and Shiang-Huei Jiang. "Neutron activation analysis using a modified absolute calibration method." Journal of Radioanalytical and Nuclear Chemistry 311, no. 2 (2016): 1201–7. http://dx.doi.org/10.1007/s10967-016-5135-4.

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27

Truong, Minh Van, Hung Minh Tran, Khang Dinh Pham, Hai Xuan Nguyen, Thang Huu Ho, and Anh Ngoc Nguyen. "Capability of gamma - gamma coincidence menthod to analyse arsenic and selenium." Science and Technology Development Journal 17, no. 2 (2014): 82–89. http://dx.doi.org/10.32508/stdj.v17i2.1317.

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The advantage of gamma – gamma coincidence method is abilities of background reduction. This technique has been studied and applications for neutron activation analysis. The experimental neutron activation analysis of geological samples, biological samples and environmental samples has been conducted by several some laboratories in the world. In this study, we would like to present the results of Arsenic and Selenium determination in geology sample by neutron activation analysis with technique of gamma – gamma coincidence measurement. By application of this gamma – gamma coincidence method, th

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28

Šimečková, Eva, Martin Ansorge, Pavel Bém, et al. "The activation of natZr by quasi-monoenergetic neutrons below 34 MeV." EPJ Web of Conferences 239 (2020): 20005. http://dx.doi.org/10.1051/epjconf/202023920005.

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Good knowledge of cross section neutron induced reactions on Zr becomes of importance due to the use of zirconium as structural material in reactors, its applicability in neutron dosimetry and the theoretical model testing. Thin Zr foils (0.05 mm thickness, 99.2% purity) were irradiated in the quasi-monoenergetic p-Li neutron fields, the proton beams from NPI CAS variable-energy cyclotron U120M at proton energies 20.33, 22.44, 24.69, 27.64, 29.85, 32.31 and 35.11 MeV. Li target with carbon stopper was used for the generation of neutron flux. The reaction 7Li (p,n) produces the high-energy quas

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29

Nurcahyani, Fatmawati, Saeful Yusuf, Istanto, et al. "Determination of Chromium Mineral in Foodstuffs in Indonesia using INAA Method." E3S Web of Conferences 481 (2024): 06001. http://dx.doi.org/10.1051/e3sconf/202448106001.

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The concentration of the element chromium (Cr) was determined in 76 types of food ingredients from four provinces in Indonesia. The element Cr is one of the essential elements needed by the human body for physiological processes. Although the amount needed for Cr is relatively small, this mineral is very important for the insulin hormone to function properly. Chromium deficiency can result in decreased insulin sensitivity, glucose intolerance and an increased risk of diabetes. The Cr element was determined using the Instrumental Neutron Activation Analysis (INAA) method in the GA. Siwabessy Mu

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Aoki, Katsumi, Tadahiro Kin, Md Kawchar Ahmed Patwary, et al. "Development of MC-based uncertainty estimation technique of unfolded neutron spectrum by multiple-foil activation method." EPJ Web of Conferences 239 (2020): 01021. http://dx.doi.org/10.1051/epjconf/202023901021.

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Unfolding process plays an important role in neutron energy distribution measurement by means of the multiple-foil activation method. We have developed an algorithm for estimating uncertainty of resultant neutron distribution. For the demonstration of the algorithm, we have conducted an experiment to measure thick-target neutron yield (TTNY) of the C(d,n) reaction induced by 20-MeV deuterons with the multiple-foil activation method. The experiment was conducted at Cyclotron and Radioisotope Center, Tohoku University in Japan. The obtained experimental data were analyzed by the algorithm. As a

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Perdikakis, G., and Et al. "Measurement of the 241Am(n,2n) Reaction Cross Section, by the Activation Method." HNPS Proceedings 13 (February 20, 2020): 144. http://dx.doi.org/10.12681/hnps.2964.

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The measurement of the cross section of the reaction 241Am(n,2n)240Am, has been performed, for the first time at neutron energies of 8.8, 9.6, 10.6 and 11.4 MeV, by the activation method. The monoenergetic neutron beam was produced at the 5.5MV TANDEM accelerator of NCSR "Demokritos", using the H{d,n) He reaction. During the 5-day long irradiation, the neutron flux was monitored by a BF3, counter. The neutron yield as well as the beam current, were recorded in 100 sec intervals by two multiscaling units. The radioactive target consisted of a 37GBq 241Am source enclosed in a Pb container. A nat

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32

Xu, Xu, Yi Chang, Wanyue Tang, et al. "Measurement of neutron yield and angular distribution for D-T neutron generator by neutron activation analysis method." Applied Radiation and Isotopes 156 (February 2020): 108971. http://dx.doi.org/10.1016/j.apradiso.2019.108971.

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Kral, Dusan, Miroslav Zeman, Karel Katovsky, Elmira Melyan, and Robert Holomb. "Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction." EPJ Web of Conferences 239 (2020): 20004. http://dx.doi.org/10.1051/epjconf/202023920004.

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Threshold activation detectors (TAD) are of great importance for a determination of neutron energy spectra and flux density. For different sources, it is necessary to choose the right combination of materials that cover the estimated spectra. Several different materials were irradiated in a quasi-monoenergetic neutron field with 29.1 MeV peak neutrons energy in the CANAM facility. Neutrons were produced in p + Li-7 reaction in a thin target and the foils were situated in the proton beam axis and close geometry to the Li target. The integral number of protons was established from accelerator te

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Vlastou, R., M. Kokkoris, M. Serris, et al. "Influence of parasitic neutrons to the 176Hf(n,2n)175Hf reaction cross section." HNPS Proceedings 18 (November 23, 2019): 83. http://dx.doi.org/10.12681/hnps.2541.

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Cross sections for 176Hf(n,2n)175Hf reaction have been measured at the VdG Tandem accelerator of NCSR \Demokritos", in the neutron energy region from 8.80 to 11.02 MeV, using the activation technique. In order to account for the contamination of the 176Hf(n,2n)175Hf by the 174Hf(n,γ)175Hf reaction activated by the presence of parasitic neutrons, an experimental method has been developed based on the influence of the parasitic neutrons in the case of the (n,2n) and (n,γ) reactions on 197Au. The results were found to be consistent with the energy spectrum of the neutron beam which has been studi

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M. M. Hosamani, A. S. Bennal, and N. M. Badiger. "Determination of the Thermal Neutron Flux by Measuring Gamma Radiations with High and Low Resolution Detectors." Journal of Nuclear Physics, Material Sciences, Radiation and Applications 6, no. 2 (2019): 187–93. http://dx.doi.org/10.15415/jnp.2019.62027.

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Thermal neutron flux (Фth) of Americium-Beryllium (Am-Be) neutron source has been measured by adopting the foil activation method. The neutrons emitted from Am-Be source are used to activate the indium-115 (115In) foil. The gamma radiations emitted from the activated isomer 116m1In are measured with NaI(Tl) and HPGe detectors. The thermal neutron flux is measured by adopting the cadmium (Cd) foil difference technique in which the Cd foil placed in front of the source to prevent the thermal neutrons from entering into the indium foil. The neutron flux is determined by measuring the gamma radiat

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36

Wakabayashi, Yasuo, Takao Hashiguchi, Yuichi Yoshimura, Maki Mizuta, Yujiro Ikeda, and Yoshie Otake. "Study of a collimation method as a nondestructive diagnostic diagnostic technique by PGNAA for salt distribution in concrete structures at RANS." EPJ Web of Conferences 231 (2020): 05007. http://dx.doi.org/10.1051/epjconf/202023105007.

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To meet strong demand for realizing an effective tool to diagnose salt distribution in concrete infrastructures, we have started a development of a new technique using a prompt gamma neutron activation analysis (PGNAA) at the RIKEN accelerator-driven compact neutron source (RANS). So far, by applying PGNAA we have experimentally confirmed that neutrons from RANS can detect small enough amounts of chlorine within the marginal concentration of around 1.2 kg/m3 to involve steel corrosion. In this study, we have proposed two methods to derive the salt depth profile which is critical information of

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37

Heftrich, Tanja, Mario Weigand, Kafa Al-Khasawleh, et al. "Activation measurements of neutron capture cross sections at various temperatures." EPJ Web of Conferences 260 (2022): 11012. http://dx.doi.org/10.1051/epjconf/202226011012.

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About 50% of the elements heavier than iron are produced during the slow neutron capture process. This process occurs in different stellar sites at various energies. To understand the ongoing nucleosynthesis, the probability of a neutron capture for different temperatures and therefore for different stellar sites is essential. Activation experiments using the 7Li(p,n) reaction as neutron source were performed. At a temperature of kBT = 25 keV the cross sections were determined for 27Al, 37Cl and 41K. A new method was developed to perform activation experiments at even lower temperatures. For a

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38

Batra, R. J., and A. N. Garg. "Determination of Manganese in Pyrolusites by Neutron Activation Analysis Using Low Flux 241Am-Be Neutron Source." Journal Geological Society of India 28, no. 4 (1986): 315–19. http://dx.doi.org/10.17491/jgsi/1986/280406.

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Abstract A neutron activation analysis method based on thermal neutron irradiation from 241Am-Be source is suggested for the determination of Mn in pyrolusites. The method uses 55Mn (n, γ) 56Mn reaction and counting of 0.847 MeV γ-rays on NaI (Tl) detector coupled with single channel analyzer. The method has been employed for the analysis of pyrolusites and results were found in good agreement with those from conventional chemical methods. The method is fast, non-destructive and economic and can be used for the determination of Mn in its ores.

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Katabuchi, T., K. Takebe, S. Umezawa, R. Fujioka, T. Saito, and M. Igashira. "Neutron capture cross section of 185Re leading to ground and isomer states of 186Re in the keV-neutron energy region." EPJ Web of Conferences 178 (2018): 03005. http://dx.doi.org/10.1051/epjconf/201817803005.

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The neutron capture cross section of 185Re was measured in the astrophysically important energy region. Measurements were made using a neutron beam from a 7Li(p,n)7Be neutron source with energies ranging from 3 to 90 keV. Two different experimental techniques, time-of-flight (TOF) and activation methods, were employed. In the TOF experiments, the total neutron capture cross section of 185Re was determined by the pulse-height weighting technique. In the activation method, the partial capture cross section leading to the ground state of 186Re was measured by detecting decay γ-rays from neutron a

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40

Koshikawa, N., A. Omata, M. Masubuchi, et al. "Activation imaging of drugs with hybrid Compton camera: A proof-of-concept study." Applied Physics Letters 121, no. 19 (2022): 193701. http://dx.doi.org/10.1063/5.0116570.

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The visualization of drugs is essential for cancer treatment. Although several methods for visualizing drugs have been proposed, a versatile method that can be easily applied to various drugs has not yet been established. Therefore, we propose “activation imaging,” in which a drug is irradiated with thermal neutrons and becomes radioactive, enabling visualization using emitted x rays and/or gamma rays. Activation imaging does not require the conjugation of specific tracers with drugs. Therefore, it can be easily applied to a variety of drugs, drug carriers (e.g., metal nanoparticles), and cont

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Brückner, Benjamin, Philipp Erbacher, Kathrin Göbel та ін. "Investigation of the ⁷Li(p,n) neutron ﬁelds at high energies". EPJ Web of Conferences 260 (2022): 11005. http://dx.doi.org/10.1051/epjconf/202226011005.

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The neutron activation method is well-suited to investigate neutron-capture cross sections relevant for the main s-process component. Neutrons can be produced via the 7Li(p,n) reaction with proton energies of 1912 keV at e.g. Van de Graaff accelerators, which results in a quasi-Maxwellian spectrum of neutrons corresponding to a temperature of kBT = 25 keV. However, the weak s-process takes place in massive stars at temperatures between 25 and 90 keV. Simulations using the PINO code [2] suggest that a Maxwellian spectrum for higher energies, e.g. kBT = 90 keV, can be approximated by a linear co

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FAGHIHI, F., S. MEHDIZADEH, and K. HADAD. "NEUTRONS FLUX DISTRIBUTIONS OF THE Pu-Be SOURCE AND ITS SIMULATION BY THE MCNP-4B CODE." International Journal of Modern Physics E 15, no. 03 (2006): 737–45. http://dx.doi.org/10.1142/s0218301306004545.

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Neutron Fluence rate of a low intense Pu-Be source is measured by Neutron Activation Analysis (NAA) of 197 Au foils. Also, the neutron fluence rate distribution versus energy is calculated using the MCNP-4B code based on ENDF/B-V library. Theoretical simulation as well as our experimental performance are a new experience for Iranians to make reliability with the code for further researches. In our theoretical investigation, an isotropic Pu-Be source with cylindrical volume distribution is simulated and relative neutron fluence rate versus energy is calculated using MCNP-4B code. Variation of t

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Sadikov, I. I., B. Kh Yarmatov, A. A. Mirsagatova, S. K. Mukhtarova, and F. Kh Rozmetova. "Instrumental neutron activation analysis of high purity rhodium." Journal of Physics: Conference Series 2984, no. 1 (2025): 012035. https://doi.org/10.1088/1742-6596/2984/1/012035.

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Abstract a method of instrumental neutron activation analysis (INAA) of pure rhodium has been developed, which does not require transferring the sample into a solution to determine the elemental composition. The method allows determining about 40 impurity elements with detection limits of n×10-5 - n×10-9 % of mass at Sr = 0.1-0.12. The method can be used to determine the microimpurity composition of ultra-pure rhodium..

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Kadem, F., N. Belouadah, and Z. Idiri. "Neutron activation analysis of certified samples by the absolute method." EPJ Web of Conferences 100 (2015): 01002. http://dx.doi.org/10.1051/epjconf/201510001002.

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Sudac, Davorin, Slavko Majetic, Robert Kollar, Karlo Nad, Jasmina Obhodas, and Vladivoj Valkovic. "Inspecting Minefields and Residual Explosives by Fast Neutron Activation Method." IEEE Transactions on Nuclear Science 59, no. 4 (2012): 1421–25. http://dx.doi.org/10.1109/tns.2011.2164936.

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Acharya, R. N., A. G. C. Nair, A. V. R. Reddy, and S. B. Manohar. "Validation of a neutron activation analysis method using k0-standardization." Applied Radiation and Isotopes 57, no. 3 (2002): 391–98. http://dx.doi.org/10.1016/s0969-8043(02)00111-2.

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Lin, X., and X. Li. "Examination of the modified monostandard method in neutron activation analysis." Journal of Radioanalytical and Nuclear Chemistry 223, no. 1-2 (1997): 47–53. http://dx.doi.org/10.1007/bf02223362.

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Lucaciu, A., L. Staicu, S. Spiridon, N. Scintee, and D. Arizan. "Multielemental determination in some water samples by neutron activation method." Journal of Radioanalytical and Nuclear Chemistry 216, no. 1 (1997): 29–31. http://dx.doi.org/10.1007/bf02034490.

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Khrbish, Y. S., and N. M. Spyrou. "Prompt gamma-ray neutron activation analysis by the absolute method." Journal of Radioanalytical and Nuclear Chemistry Articles 151, no. 1 (1991): 55–61. http://dx.doi.org/10.1007/bf02040130.

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Tashmetov M. Yu., Makhkamov Sh ., Tillaev T. S., Erdonov M. N., and Kholmedov H. M. "Determination of solubility of cobalt in singlecrystal silicon method neutron activation." Physics of the Solid State 65, no. 4 (2023): 526. http://dx.doi.org/10.21883/pss.2023.04.55990.557.

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The possibility of instrumental neutron activation analysis is revealed for determining the solubility of cobalt in single-crystal silicon. It was shown that in n-Si in the diffusion temperature range of 1000-1250oC the total solubility of the 60Co impurity varies within the concentration range of 2.8·1014-9·1015 cm-3, and the electrically active concentration grows from 1013 to 3·1014 cm-3. In order to reduce the error in determining the concentration of 1013 in doped Si samples, it is suggested to use the parent stable isotope rather than the daughter cobalt radionuclide. Keywords: monocryst

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