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Determination of the Average Neutron Activation Cross Section with an Annular-Shaped 241Am/Be Neutron Source and a NaI(T1) Detector for the 27Al(n,p)27Mg reaction

机译：用环形241am / Be中子源和NaI（T1）探测器测定27al（n，p）27mg反应的平均中子活化截面

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摘要

The average neutron activation cross section was determined with an annular-shaped 241 Am/Be neutron source and an Nal(T1) detector. The calculated average neutron flux in the center of the cavity space of the source is used with the experimental data to give the average neutron activation cross section for the 27Al(n,p)27Mg reaction. The mean value of the measured neutron activation cross section is (17.5 + or - 3.5)mb.

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Rieppo, R.;
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年度 1984
页码 p.1-12
总页数 12
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Neutron activation analysis; Americium 241; Beryllium compounds; Neutron sources; Activation energy; Aluminum 27; Flux (Rate); Magnesium isotopes; Neutron irradiation; Nuclear reactions;

机译：中子活化分析; americ 241;铍化合物;中子源;活化能;铝27;通量（速率）;镁同位素;中子辐照;核反应;

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1. Absolute Measurements of Activation Cross Sections of 27Al(n, p)27Mg, 27Al(n, α)24Na, 56Fe(n, p)56Mn, 90Zr(n, 2n)89m+gZr and 93Nb(n, 2n)92mNb at Energy Range of 13.314.9 MeV [J] . Yujiro IKEDA, Chikara KONNO, Yukio OYAMA, Journal of nuclear science and technology . 1993,第9期

机译：能量处27Al（n，p）27Mg，27Al（n，α）24Na，56Fe（n，p）56Mn，90Zr（n，2n）89m + gZr和93Nb（n，2n）92mNb激活截面的绝对测量13.314.9 MeV的范围
2. Cross section measurements of a few threshold reactions induced by fast neutrons from an Am/Be source: Integral tests of differential neutron reaction cross section data [J] . Qaim S.M., Uddin M.S., Hossain S.M., Radiochimica Acta: International Journal for Chemical Aspects of Nuclear Science and Technology . 2013,第4期

机译：来自Am / Be来源的快速中子引起的一些阈值反应的横截面测量：差分中子反应横截面数据的整体测试
3. The determination of reactor neutron spectrum-averaged cross-sections in miniature neutron source reactor facility. [J] . Jonah SA, Ibrahim YV, Akaho EH Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine . 2008,第10期

机译：微型中子源反应堆设施中反应堆中子谱平均截面的确定。
4. A multi-detector NaI(Tl) gamma-ray spectrometry system for investigation of neutron induced capture and fission reactions [C] . I. Ruskov, Yu. N. Kopach, V. Skoy, GAMMA-2 Scientific Workshop on the Emission of Prompt Gamma-Rays in Fission and Related Topics . 2015

机译：用于研究中子诱导捕获和裂变反应的多探测器Nai（TL）γ射线光谱系统
5. Neutron flux and energy characterization of a plutonium-beryllium isotopic neutron source by monte carlo simulation with verification by neutron activation analysis. [D] . Harvey, Zachary R. 2010

机译：mon-铍同位素中子源的中子通量和能量表征，通过蒙特卡罗模拟并通过中子活化分析进行验证。
6. Commissioning of the NPDGamma Detector Array: Counting Statistics in Current Mode Operation and Parity Violation in the Capture of Cold Neutrons on B4C and 27Al [O] . M. T. Gericke, J. D. Bowman, R. D. Carlini, 2005

机译：NPDGamma检测器阵列的调试：在B4C和27Al上捕获冷中子时电流模式操作中的计数统计和违反中子奇偶校验
7. Determination of Emission Rates and Spectra of Neutrons from 241Am–Li Sources [O] . Katsuya Hoshi, Sho Nishino, Tadayoshi Yoshida, 2019

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8. DROSG-87: Neutron source reactions. Version 3.20 (Sept. 1994). Angular dependences of neutron energies, cross sections and neutron yields for 13 monoenergetic neutron source reactions. Summary documentation [R] . Drosg, M. , Schwerer, O. 1994

机译：DROsG-87：中子源反应。版本3。20（1994年9月）。 13个单能中子源反应的中子能量，截面和中子产额的角度依赖性。摘要文档

Determination of the Average Neutron Activation Cross Section with an Annular-Shaped 241Am/Be Neutron Source and a NaI(T1) Detector for the 27Al(n,p)27Mg reaction

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