• 제목/요약/키워드: (n,p) reaction cross-section

검색결과 12건 처리시간 0.022초

The Reaction Probability and the Reaction Cross-section of N + O2→ NO + O Reaction Computed by the 6th-order Explicit Symplectic Algorithm

  • He, Jianfeng;Li, Jing
    • Bulletin of the Korean Chemical Society
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    • 제27권12호
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    • pp.1976-1980
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    • 2006
  • We have calculated the reaction probability and the reaction cross-section of the $N(^4S)+O_2(X^3\sum_{g}^{-})\;\rightarrow\;NO(X^2\Pi)+O(^3P)$ reaction by the quasiclassical trajectory method with the 6th-order explicit symplectic algorithm, based on a new ground potential energy surface. The advantage of the 6th-order explicit symplectic algorithm, conserving both the total energy and the total angular momentum of the reaction system during the numerical integration of canonical equations, has firstly analyzed in this work, which make the calculation of the reaction probability more reliable. The variation of the reaction probability with the impact parameter and the influence of the relative translational energy on the reaction cross-section of the reaction have been discussed in detail. And the fact is found by the comparison that the reaction probability and the reaction cross-section of the reaction estimated in this work are more reasonable than the theoretical ones determined by Gilibert et al.

Study on (n,p) reactions of 58,60,61,62,64Ni using new developed empirical formulas

  • Yigit, Mustafa
    • Nuclear Engineering and Technology
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    • 제52권4호
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    • pp.791-796
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    • 2020
  • Nuclear fusion seems to be a good choice of energy source in the future. Nickel is one of the crucial structural materials for fusion devices. In this work, the cross section data of 58Ni(n,p)58Co, 60Ni(n,p)60Co, 61Ni(n,p)61Co, 62Ni(n,p)62Co and 64Ni(n,p)64Co reactions were calculated using the nuclear codes ALICE/ASH, EMPIRE 3.2 and TALYS 1.8. In addition, the cross sections were calculated with the empirical formulas obtained in our previous paper at 14-15 MeV. The obtained results were compared with the measured values in the literature, and with the evaluated data files (JEFF-3.3, TENDL-2017, ENDF/B-VIII.0).

Neutron Cross Section Evaluation on Dy Isotopes

  • Lee, Y. D.;J. H. Chang
    • Nuclear Engineering and Technology
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    • 제34권2호
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    • pp.154-164
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    • 2002
  • Neutron cross section data on Dy-160, Dy-161, Dy-162, Dy-163 and Dy-164 were calculated and evaluated in the energy range of 1 keV to 20 MeV using a spherical optical model, statistical model and pre-equilibrium model. The energy dependent optical model potential parameters were obtained based on the recent experimental data. The width fluctuation correction in Hauser-Feshbach particle decay and the quantum mechanical approach in pre-equilibrium analysis were introduced and gave a better cross section calculation in EMPIRE-II. The total, elastic scattering and threshold reaction cross sections were evaluated and compared with the evaluated files. The model calculated (n, tot), (n, ${\gamma}$) and (n, p) cross sections were in good agreement with the experimental data in the measured energy range. The results will be applied to ENDF/B-VI for data improvement.

Model-based predictions for nuclear excitation functions of neutron-induced reactions on 64,66-68Zn targets

  • Yigit, M.;Kara, A.
    • Nuclear Engineering and Technology
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    • 제49권5호
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    • pp.996-1005
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    • 2017
  • In this paper, nuclear data for cross sections of the $^{64}Zn(n,2n)^{63}Zn$, $^{64}Zn(n,3n)^{62}Zn$, $^{64}Zn(n,p)^{64}Cu$, $^{66}Zn(n,2n)^{65}Zn$, $^{66}Zn(n,p)^{66}Cu$, $^{67}Zn(n,p)^{67}Cu$, $^{68}Zn(n,p)^{68}Cu$, and $^{68}Zn(n,{\alpha})^{65}Ni$ reactions were studied for neutron energies up to 40 MeV. In the nuclear model calculations, TALYS 1.6, ALICE/ASH, and EMPIRE 3.2 codes were used. Furthermore, the nuclear data for the (n,2n) and (n,p) reaction channels were also calculated using various cross-section systematics at energies around 14-15 MeV. The code calculations were analyzed and obtained using the different level densities in the exciton model and the geometry-dependent hybrid model. The results obtained from the excitation function calculations are discussed and compared with literature experimental data, ENDF/B-VII.1, and the TENDL-2015 evaluated data.

Study on (n,p) reactions of 58Ni, 99Tc, 99Ru, 131Xe, 133Cs and 186Os radioisotopes used in medicine

  • Hallo M. Abdullah;Ali H. Ahmed
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.304-309
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    • 2023
  • In the last decade, nuclear medicine appears to be a good choice of medicine. 58Co, 99Mo, 99Tc, 99Re, 133Xe and 186Re are very important radionuclides for nuclear medicine. In this study, the excitation functions of 58Ni (n, p) 58Co, 99Tc (n, p) 99Mo, 99Ru (n, p) 99Tc, 131Xe (n, p) 131I, 133Cs (n, p) 133Xe and 186Os (n, p) 186Re nuclear reactions were calculated at neutron energies between 1 and 20 MeV using TALYS 1.95 and EMPIRE 3.2 nuclear codes. Furthermore, the cross sections were calculated with the empirical formula derived in our past study at 14-15 MeV. The obtained results were compared with the measured values in EXFOR library, and with the evaluated data of (JENDL-4.0/HE, JEFF-3.3, TENDL-2019, ENDF/B-VIII.0, IRDFF-II, JENDL/ImPACT-18). The results are in good agreement with those of the evaluated data libraries and experimental results and indicates that these radioisotopes can be produced by smaller cyclotrons.

NUCLEAR DATA MEASUREMENT OF 186RE PRODUCTION VIA VARIOUS REACTIONS

  • Bidokhti, Pooneh Saidi;Sadeghi, Mahdi;Fateh, Behrooz;Matloobi, Mitra;Aslani, Gholamreza
    • Nuclear Engineering and Technology
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    • 제42권5호
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    • pp.600-607
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    • 2010
  • Rhenium-186, having a half-life of 90.64 h, is an important radionuclide, used in metabolic radiotherapy and radio immunotherapy. $^{186}Re$ hydroxyethylidene diphosphonate (HEDP) is a new compound used for the palliation of painful skeletal metastases. Its production is achieved via charged-particle-induced reactions; the data are available in EXFOR library. For the work discussed in this paper, production of $^{186}Re$ was done via $^{nat}W(p,n)^{186}Re$ nuclear reaction. Pellets of $^{nat}W$ were used as targets and were irradiated with 15, 17.5, 20, 22.5, 25 MeV proton beams at 5 ${\mu}A$ current. The radiochemical separation was performed by the ion exchange chromatography method. The production yield achieved at 25 MeV was 1.91 $MBq{\cdot}{\mu}A^{-1}{\cdot}h^{-1}$. Excitation functions for the $^{186}Re$ radionuclide, via $^{186}W(p,n)^{186}Re$ and $^{186}W(d,2n)^{186}Re$ reactions were calculated by ALICE-ASH and TALYS-1.0 codes to validate and fit the experimental data and to obtain a recommended set of data for $^{186}W(p,n)^{186}Re$ reaction. Required thickness of the targets was obtained by SRIM code for each reaction.

핵임계사고시(核臨界事故時)에 있어서 속중성자선량(速中性子線量) 측정(測定) (Fast Neutron Dosimetry in Nuclear Criticality Accidents)

  • 육종철;노성기
    • Journal of Radiation Protection and Research
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    • 제2권1호
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    • pp.17-23
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    • 1977
  • 여러가지 핵분열중성자(核分裂中性子) 스펙트럼에 $^{32}S(n,\;p),\;^{27}Al(n,\;{\alpha})$$^{115}In(n\;n')$ 여기함수(勵起函數)를 증율(增率)시켜 평균핵반응단면적(平均核反應斷面積)을 전자계산기(電子計算機)로 계산(計算)하였다. 그 결과(結果) 발단(發端)에너지가 높을수록 중성자(中性子)스펙트럼 변화(變化)에 따라 평균(平均) 단면적(斷面積)은 민감(敏感)하게 변화(變化)한다는 것이 판명(判明)되었다. 발단(發端)에너지가 비교적(比較的) 낮은 인디움의 경우(境遇), 핵분열특성(核分裂特性)에 따라 그의 평균(平均) 단면적(斷面積)은 크게 변화(變化)되지 않았는데 중성자(中性子) 산란작용(散亂作用)에 의(依)한 영향(影響)이 배제(排除)될 수만 있다면 인디움은 핵임계사고시(核臨界事故時)에 방출(放出)되는 중성자(中性子)의 적산계(積算計)로서 효과적(效果的)으로 사용(使用)될 수 있을 것 같았다. 더욱이 중성자선량환산인자(中性子線量換算因子)가 핵분열(核分裂) 중성자(中性子)스펙트럼에 거의 무관(無關)하다는 사실(事實)은 인디움을 핵임계사고시(核臨界事故時)의 중성자선량적산계(中性子線量積算計)로 사용할 수 있음을 뒷받침하는 것 같았다.

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중금속 오염이 n형 실리콘 태양전지의 전기적 특성에 미치는 영향에 대한 연구 (Influence of Metallic Contamination on Photovoltaic Characteristics of n-type Silicon Solar-cells)

  • 김일환;박준성;박재근
    • Current Photovoltaic Research
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    • 제6권1호
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    • pp.17-20
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    • 2018
  • The dependency of the photovoltaic performance of p-/n-type silicon solar-cells on the metallic contaminant type (Fe, Cu, and Ni) and concentration was investigated. The minority-carrier recombination lifetime was degraded with increasing metallic contaminant concentration, however, the degradation sensitivity of recombination lifetime was lower at n-type than p-type silicon wafer, which means n-type silicon wafer have an immunity to the effect of metallic contamination. This is because heavy metal ions with positive charge have a much larger capture cross section of electron than hole, so that reaction with electrons occurs much more easily. The power conversion efficiency of n-type solar-cells was degraded by 9.73% when metallic impurities were introduced in the silicon bulk, which is lower degradation compared to p-type solar-cells (15.61% of efficiency degradation). Therefore, n-type silicon solar-cells have a potential to achieve high efficiency of the solar-cell in the future with a merit of immunity against metal contamination.

A Fast Neutron Time-of-Flight Spectrometer with High Resolution

  • Cho, Mann
    • Nuclear Engineering and Technology
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    • 제4권2호
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    • pp.116-131
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    • 1972
  • Li$^{7}$ (p, n) Be$^{7}$ 원자핵반응에서 Li target의 두께와 입사양자의 에너지를 적절히 선정하므로써 1-n sec 파동 Van de Graaff 가속도로부터 keV 영역에서의 연속중성자spectrum을 발생시키고 92% 농축된 5mm 두께의 $B^{10}$ 판과 4개의 4"$\times$3" NaI (T1) 발광체로 이루어진 속중성자검출기를 이용 속중성자 비행시간법에 의한 중성자spectrometer 를 제작하였다. 장치의 에너지 분해능은 50 keV에서 0.3%보다 양호하며 신호대잡음비도 개량되었다. 이를 이용하여 몇가지 분석된 단일동위원소의 전단면적을 측정하고 R-matrix 전자계산 code로 분석하였다. 각 공명에 따르는 스핀식와 공명인수들을 찾아내었다.

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