共查询到16条相似文献,搜索用时 125 毫秒
1.
The fluence rate distribution of neutrons in the reactionsof 50MeV/u ^18O-ion on thick Be,Cu and Au targets have been measured with an activation method of threshold detectors andthe neutron dose equivalent rate distributions at 1m from the tqrgets in intermediate energy heavy ion target area are obtained by using the conversion factors from neutron fluence rate to neutron doseequivalent rate. 相似文献
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Total neutron yields and neutron emission rates in the forward direction for 50MeV/u ^18O-ion on thick Be,Cu,Au targets have been measured using an activation technique.The results indicate that neutron yields and emission rates in the forward direction depend on the atomic number of target nuclei,i.e.the lighter target the greater neurtron yield and neutron emission rate.Meanwhile,the neutron yield of ^18O-ion is greater than that of 12C-ion when target nucleus and incident energy per nucleon are identical. 相似文献
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Fluence rates and angular distributions of the neutron emitted by 75MeV/u ^12C-ion bombardment on thick Be and Au targets have been measured by means of the threshold detector activation method.Based on that,the neutron yields,emission rates in the forward direction and neutron dose equivalent rate distributions were deduced. 相似文献
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The distribution of neutrons produced by the reaction of 50MeV/u ^12C-ion on a thick Cu target are studied.The neutrons are measured with threshold activation detectors.Al.F,C,Al and In activation samples were used to measure neutrons with energy greater than 7,11,20,50MeV and thermal neutrons,respectively,The fluence rate,energy and angular distributions of neutrons,total neutron yield of 12C-ion and the emission rate in the forward direction of neutrons over 11 and 20MeV were obtained. 相似文献
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The Possibility of using 209Bi as a new threshold detector to measure high-energy neutrons was investigated for the first time.At the same time the experiment measured successfully the emitted neutron fluence rate,energy spectrum and dose equivalent rate distributions in the heavy ion target area using a detector complex including 209Bi,^115In,^27Al,^19Fand ^12C samples. 相似文献
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ZHOU Pei-de FANG Bang-cheng 《中国原子能科学研究院年报》2005,(1):8-9
The delayed neutron detection(DND) system is one of the failed fuel detection systems designed for China Experimental Fast Reactor (CEFR). This paper gives the analysis results of the delayed neutron flux and the fission neutron flux compared to background. The code package which contains codes such as VVER, VITAMIN-C, PASC-1 and MORSE, was used to analyze. The VVER code was used to calculate the releasing rate of volatile fission products (^87Br, ^88Br and ^137I) from fuel pellet to the gas plenum of fuel rod. The VITAMIN-C library and the cross section processing system PASC-1 were used to produce the ANISN format library for neutron transport calculation. The MORSE code was used to transport calculation of the fission neutron and the delayed neutron, respectively. For CEFR, 相似文献
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ZHANGGuo-Hui LUHan-Lin 《核技术(英文版)》2001,12(3):161-164
The cross sections of the ^75As(n,γ)^76As reaction were measured in the neutron energy range from 0.50 to 1.50 MeV by using the activation technique.Neutrons were produced via the T(p,n)^3He reaction and the cross sections of the ^197Au(n,γ)^198Au reaction were used to determine the absolute neutron flux.Present results are compared with existing measurements and evaluations. 相似文献
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《中国核科技报告》1999,(Z1)
Ga is an important nucleus in nuclear science and engineering. However, its experimental data are less and the calculation is necessary. Based on the available experimental data of ~(69,71,Nat)Ga and the nuclear reaction semi-classical theory code SUNF, neutron induced reaction cross sections, angular distributions and the energy spectrum were calculated for ~(69,71)Ga at incident neutron energy below 20 MeV. The calculated results were compared with the experimental data. 相似文献
9.
HUANG Xiao-long 《中国原子能科学研究院年报》2006,(1):114-114
Based on the experimental data of total, nonelastic, elastic cross section and elastic scattering angular distributions for n+^60Ni reactions, a set of neutron optical model potential parameters is obtained in the region of incident neutron energy from 0.456-150 MeV. The reaction cross sections, angular distributions, energy spectra, gamma-ray production cross sections, gamma-ray production energy spectra, are calculated and evaluated by optical model, 相似文献
10.
MENG Yan-tai WANG Xiao-zhong HE Li-xia BAI Lei SHAO Jie-wen ZHU Li-qun 《中国原子能科学研究院年报》2006,(1):190-190
We have adopted active neutron coincidence method and y-ray measurement method in order to measure the attributes of fast neutron reactor's fresh fuel. An improved uranium neutron coincidence collar (UNCC) was used for measuring the ^235U enrichment distribution of the 2 pieces fuel assembles. The measured results show curve's trend is the same as the fact of distribution. Fig. 1 shows the assembly's neutron coincidence counting rate. 相似文献
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中能^12C重离子在Fe等厚靶上核反应的中子产额和能谱 总被引:1,自引:1,他引:0
本文调研了由测量和核内级联-蒸发模型理论计算得到的中能区重离子核反应中子发射微分截面数据,并依据这些结果计算给出了单核能为58.3和100MeV 的~(12)C 离子轰击~(56)Fe 厚靶产生的次级中子能谱、角分布和总产额。同时对现有数据做了较为细致的分析,为重离子的防护提供了一些基础资料。 相似文献
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双闪烁体快中子飞行时间谱仪 总被引:2,自引:0,他引:2
一台由散射闪烁体和中子探测器及其屏蔽准直系统、α粒子探测器和相应的电子学仪器组成的双闪烁体快中子飞行时间谱仪已经建立,并在研究D(n,n)D和D(n,2n)P反应中获得了满意的结果,文章介绍了它的工作原理、结构、主要性能和应用。 相似文献
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T. Ogawa M.N. MorevT. Iimoto T. Kosako 《Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms》2011,269(17):1929-1939
Spallation and neutron capture reaction rate distributions were measured using activation detectors inside a 90-cm thick ordinary concrete pile exposed to a field of secondary particles escaping a thick (stopping length) iron target bombarded with various intermediate energy ions, 230 MeV/u He, 400 MeV/u C, and 800 MeV/u Si. Activation detectors of aluminum, bismuth, gold, and gold covered with cadmium were inserted at various depths in the concrete pile. In addition, the distributions of activation reaction rate were simulated by FLUKA and PHITS Monte-Carlo codes. Generally, comparison of measured and calculated reaction rates show agreement within a factor of two. The experimental data will be useful for benchmarking Monte-Carlo radiation transport simulation code capabilities in estimating radioactivity induced in accelerator radiation shielding. 相似文献