• 제목/요약/키워드: n,${\alpha}$) reaction cross-section

검색결과 6건 처리시간 0.025초

Neutron yield and energy spectrum of 13C(alpha,n)16O reaction in liquid scintillator of KamLAND: A Nedis-2m simulation

  • Vlaskin, Gennady N.;Bedenko, Sergey V.;Ghal-Eh, Nima;Vega-Carrillo, Hector R.
    • Nuclear Engineering and Technology
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    • 제53권12호
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    • pp.4067-4071
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    • 2021
  • The 13C (α,n)16O reaction cross-section is important data for nuclear physics, astrophysical, and neutrino physics experiments, however, they exhibit uncertainties due to the discrepancies in the experimental data. In this study, using the Nedis-2m program code, the energy spectrum of α-induced neutrons in a thin carbon target was calculated and the corresponding reaction cross-section was refined in the alpha particle energy range of 5-8 MeV. The results were used to calculate the intensity and energy spectrum of background neutrons produced in the liquid scintillator of KamLAND. The results will be useful in a variety of astrophysical and neutrino experiments especially those based on LS or Gd-LS detectors.

연속에너지 중성자에 대한 천연 Sm의 중성자 포획단면적 측정 (Measurement of Energy Dependent Differential Neutron Capture Cross-section of Natural Sm by Using a Continuous Neutron Flux below)

  • 윤정란
    • 한국방사선학회논문지
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    • 제10권5호
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    • pp.337-341
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    • 2016
  • 중성자에너지 영역 0.003 eV에서 10 eV에 대해 천연 Sm의 Sm(n,${\gamma}$) 반응에 대한 중성자 포획단면적을 측정하였다. 교토대학교 원자로실험소의 46-MeV 전자선형가속기에서 발생되는 전자의 광핵반응에 의한 중성자를 사용하였고 TOF 방법으로 측정하였다. 사용한 검출기는 12개의 BGO($Bi_4Ge_3O_{12}$) 섬광체로 구성되었고 이 검출장치로 Sm(n,${\gamma}$) 반응으로부터 나오는 즉발감마선을 측정하였다. 검출장치는 중성자 생성 위치로부터 $12.7{\pm}0.02m$ 위치에 설치되었으며 $^{10}B(n,{\alpha}{\gamma})^7Li$ 반응을 이용해 Sm 시료에 입사되는 중성자 선속을 구하였다. 또한 중성자 선속의 변화를 확인하기 위해 $BF_3$ 검출기로 모니터링 하였다. Sm(n,${\gamma}$) 반응단면적 측정결과는 BROND 2.2에 의한 평가결과와 J. C. Chou 및 V. N. Kononov 의 측정값과 비교하였다.

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.

Scattering cross section for various potential systems

  • Odsuren, Myagmarjav;Kato, Kiyoshi;Khuukhenkhuu, Gonchigdorj;Davaa, Suren
    • Nuclear Engineering and Technology
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    • 제49권5호
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    • pp.1006-1009
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    • 2017
  • We discuss the problems of scattering in this framework, and show that the applied method is very useful in the investigation of the effect of the resonance in the observed scattering cross sections. In this study, not only the scattering cross sections but also the decomposition of the scattering cross sections was computed for the ${\alpha}-{\alpha}$ system. To obtain the decomposition of scattering cross sections into resonance and residual continuum terms, the complex scaled orthogonality condition model and the extended completeness relation are used. Applying the present method to the ${\alpha}-{\alpha}$ and ${\alpha}-n$ systems, we obtained good reproduction of the observed phase shifts and cross sections. The decomposition into resonance and continuum terms makes clear that resonance contributions are dominant but continuum terms and their interference are not negligible. To understand the behavior of observed phase shifts and the shape of the cross sections, both resonance and continuum terms are calculated.

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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Study on (n, α) reactions for the production of 51Cr, 89Sr, 99Tc, 131I, 133Xe, 137Cs and 153Sm radioisotopes used in nuclear medicine

  • Hallo M. Abdullah;Ali H. Ahmed
    • Nuclear Engineering and Technology
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    • 제55권9호
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    • pp.3352-3358
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    • 2023
  • Nuclear medicine seems to be a decent choice of medicine in the recent decade. The radioactive isotopes 51Cr, 89Sr, 99Tc, 131I, 133Xe, 137Cs and 153Sm are extremely essential in nuclear medicine. The excitation functions of the 54Fe (n, α) 51Cr, 92Zr (n, α) 89Sr, 102Rh (n, α) 99Tc, 134Cs (n, α) 131I, 136Ba (n, α) 133Xe, 140La (n, α) 137Cs and 156Gd (n, α) 153Sm reactions were calculated in this study using the EMPIRE 3.2.3 and TALYS 1.95 nuclear codes. Additionally, the cross sections at 14-15 MeV were calculated using empirical formulae and the experimental data. The computer codes were compared to the experimental data and Empirical formulas as well as the evaluated data (TENDL 2021, JENDL 3.3, JENDL 5, JEFF 3.3, EAF 2010, CENDL 3.1, CENDL 3.2, ROSFOND 2010, FENDL 3.2 b, and BROND 3.1).