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- 검색키워드
- 주제어 : Activation foil method (검색결과 4 건)
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M. Sakama,T. Saze,K. Maeda,K. Akamatsu,E. Honda,H. Nishitani 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The role of systematic evaluations of thermal neutron fluxes originated in various medical small radiation accelerator facilities has become more and more important to establish uniformly a clearance system about radioactivities of radioactive waste materials produced, for example, when those facilities would be decommissioned and improved. The purpose of this paper was to investigate the distribution of thermal neutron fluxes into the self-shielded wall at the PET cyclotron in Tokushima University Hospital.The distribution of thermal neutron fluxes was determined using the activation Au foil method of <sup>197</sup>Au(n,γ)<sup>198</sup>Au reaction and the visualization was observed using the imaging plate (IP) of a long ribbon shaped activation Au thin foil. It was found that the thermal neutron fluxes were distributed from 6.65 × 10^6 cm^(-2) s^(-1) (at 1.5 cm distance from an inside wall into a polyethylene layer) to 1.20 × 10^2 cm^(-2) s^(-1) (at 71.0 cm distance into a heavy concrete layer), and also that the distribution trend of thermal neutron fluxes will be approximately consistent with that of the calculated data led by MCNP code. We have confirmed that it will be possible for the IP visualization of thermal neutron fluxes into the self-shielded wall at the PET cyclotron to reproduce those distribution quantitatively and over a wide area.
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Initial result of neutron energy spectrum reconstruction using multi-foil activation method in KSTAR
Jo, Jungmin,Cheon, MunSeong,Chung, Kyoung-Jae,Hwang, Y.S. Elsevier 2018 Fusion engineering and design Vol.136 No.1
<P><B>Abstract</B></P> <P>For the purpose of the fusion power measurement accuracy improvement in KSTAR, multi-foil activation method has been applied on KSTAR neutron activation system (NAS). In order to increase the spectral coverage, in addition to indium and silicon samples which have been routinely used to measure fusion power of deuterium plasma and triton burnup respectively, 3 other sample materials, aluminum, niobium, and nickel are selected based on the calculation of expected activity and <I>γ</I>-ray counts. Due to the limited accessibility in counting station during the plasma experiment, and in order to maximize <I>γ</I>-ray counting statistics each sample material is irradiated one by one during the 2016 KSTAR campaign. In this reason, the analysis is carried out under the assumption that neutron emission characteristics on each plasma discharge do not change. MAXED unfolding code has been used in order to reconstruct the default spectrum which is calculated by MCNP5. This initial reconstruction result will be used as criterion for selection of additional appropriate reaction and optimization of strategies of sample irradiation and <I>γ</I>-ray counting.</P>
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Measurement of production cross sections in proton induced reactions on natural zirconium
Yang, Sung-Chul,Jung, Myung Hwan,Kim, Guinyun,Lee, Young-Ouk Elsevier 2018 Nuclear instruments & methods in physics research. Vol.436 No.-
<P><B>Abstract</B></P> <P>The production cross sections of <SUP>90g,92m,95g</SUP>Nb, <SUP>86,88,89g,95</SUP>Zr, <SUP>86g,87m,87g,88</SUP>Y, <SUP>85g</SUP>Sr, and <SUP>83</SUP>Rb in a proton induced nuclear reaction of natural zirconium were measured within the proton energy range of 35.7–66.6 MeV at the Korea Multi-purpose Accelerator Complex (KOMAC), Gyeongju, Korea. The excitation functions of radionuclides produced from the <SUP>nat</SUP>Zr(p,x) reactions were determined through a stacked-foil activation method and an off-line γ-ray spectroscopy. A high purity germanium (HPGe) detector was used to measure the induced activities of the radionuclides. The incident beam energy in each foil was calculated from the SRIM code. The proton flux was determined by using the <SUP>nat</SUP>Cu(p,x)<SUP>62</SUP>Zn monitor reaction. The measured data were compared with the experimental data in the literature and the data from the TENDL-2017 library based on the TALYS code. The present results are in general agreement with the literature data and in some cases with the calculated data from the TENDL-2017 library. However, in some of the cases, the calculated data from the TENDL-2017 library overestimate or underestimate the experimental data.</P>
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양성철,윤상필,송태영,김귀년 한국원자력학회 2024 Nuclear Engineering and Technology Vol.56 No.5
The production cross sections of 55,56,57Co, 52gFe, 52g,54Mn, 51Cr, and 48V from the natFe (p,x) reactions were measured using a proton energy of 57 MeV at the Korea Multi-purpose Accelerator Complex (KOMAC) in Gyeongju, Korea. The conventional stacked-foil activation method and offline γ-ray spectroscopy were used to determine the excitation functions of proton induced nuclear reactions on iron. The measured excitation functions were compared with experimental data in literature and theoretical data from the TENDL-2021 library. The present data show generally good agreement with other experimental data, but discrepancies were found between the present data and the excitation functions of the TENDL-2021 library in the investigated energy range, except for 56,57Co and 54Mn.
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