共查询到19条相似文献,搜索用时 187 毫秒
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为了解决DPF实验中经常出现的首次中子产额不稳定、中子波形经常出现双峰以及每次充氘后稳定放电实验次数较少的问题,特地研制了双真空烘烤排气装置。 相似文献
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针对点堆动力学理论解释脉冲源法测试原理时存在的问题, 基于无源中子输运方程分析次临界系统总中子数、泄漏γ射线计数率随时间的变化关系。理论分析表明: 脉冲中子源作用结束后(无源条件下), 在一定时间范围内, 泄漏γ射线计数率和总中子数近似成正比, 两者随时间变化服从近似指数衰减规律, 反映系统本身的裂变衰减特性, 可以由总中子数和γ射线计数率求解瞬发中子衰减时间常数。基于蒙特卡罗程序构造类Godiva裸铀球次临界系统, 模拟脉冲中子源作用下中子和γ射线输运过程, 计算总中子数、泄漏γ射线计数率及两者比值随时间的变化关系, 结果与理论分析一致; 利用脉冲源法由总中子数、泄漏γ射线计数率计算瞬发中子衰减时间常数α0, 得到与α-k迭代一致的α0。说明总中子数、泄漏γ射线计数率可以准确反映系统本身的裂变衰减特性。此外, 根据理论分析和模拟计算给出脉冲源法可用数据的时间范围, 分析泄漏γ射线计数率和总中子数比值的影响因素。 相似文献
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光电倍增管对14 MeV脉冲中子的直照响应 总被引:1,自引:1,他引:0
采用ING-103型DPF脉冲中子源产生的14.1 MeV脉冲中子对EMI两个不同型号的光电倍增管EMI-9815B和EMI-9850B进行了直照实验。针对DPF脉冲中子源产生中子脉冲的同时也会产生X射线脉冲的特点,采取了飞行时间法及吸收衰减法来消除X射线对中子脉冲的干扰。利用中子及X射线速度的差异,将光电倍增管放置在离源较远的测点位置,测得了X射线脉冲和中子脉冲时间上错开的双峰波形。通过在辐射通道内添加5 cm厚的铅吸收体有效地抑制了X射线峰,在离源较近的测量位置测到了干净的脉冲中子波形。根据实测波形,得到的光电倍增管EMI-9815B和EMI-9850B中子直照灵敏度分别为10-13与10-15量级,该结果与理论计算结果在量级上一致。 相似文献
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无损检测用15MeV电子直线加速器主束内光中子剂量的测量与MC模拟计算 总被引:1,自引:0,他引:1
通过实验和模拟计算研究了无损检测用15MeV电子直线加速器X射线主束内的中子剂量. 加速器采用了铜复合靶和钨加含硼聚乙烯的屏蔽结构, 能够有效地减少光中子的产生, 中子产额在1/1000n/γ以下. 但由于主束内光子剂量很大, 中子的绝对强度也不容忽视. 针对加速器周围强X射线脉冲辐射场的特点, 采用了被
动型的中子剂量测量方法, 加速器正常工作情况下, 使用CR-39片和双电离室测量了等中心处中子对X射线的剂量当量比率, 分别为0.19mSv/Gy X-ray和0.060mSv/Gy X-ray. 利用MCNP5模拟计算了实验相应点的中子对X射线的剂量当量比率, 为0.092mSv/Gy X-ray, 与实验测量结果在数量级上一致. 加速器主射束上Dn/Dγ<1/1000,小于辐射防护标准对中子泄漏剂量的规定值, 从而验证了屏蔽结构的安全性. 相似文献
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主要介绍了一种用于进行脉冲中子波形和产额测量的闪烁探测器,它由双套独立探测系统组成,可靠性高,在没有脉冲中子的场合,为了检验探测器各通道是否正常工作,在电子线路部分增加了脉冲产生单元,通过脉冲产生单元的定时脉冲控制发光二极管周期性发光,这样可以实时监控探测器工作是否正常,并且监控信号不影响正常的中子脉冲波形。 相似文献
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为了解决蒙特卡罗模拟S(, )模型只能求解特定温度条件下中子输运问题的局限性,建立了中子在不同温度液态水中输运的等效质量热运动模型。在分析自由气体热运动模型的基础上,采用不同的等效质量对中子与水中氢原子的弹性散射模拟过程进行改进,对中子穿过水层后的流量进行模拟计算,通过与S(, )模型的计算结果的比较,得到了5个不同的温度点水中氢原子的最佳等效质量。根据5个不同温度点的数据拟合给出了最佳等效质量和温度的函数关系。采用该模型计算得到的中子在不同温度条件下水中输运参数与S(, )模型相符。等效质量热运动模型突破了S(, )模型只能计算有限温度点的局限性,能有效处理300~800 K任意温度水中的中子输运问题。 相似文献
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铁的次级中子双微分截面对核装置的设计、运行与维护具有重要作用。相关实验数据缺乏,且评价数据不完善,需要使用可靠的核理论模型进行计算。本工作利用GEANT4程序结合不同的中子评价数据计算了8.17, 11.5, 14.1和18 MeV等入射能量下中子轰击薄铁靶不同出射角度的次级中子双微分截面;同时利用TALYS程序和GEANT4程序结合BIC、BERT和INCLXX模型计算了25.7, 65, 100和150 MeV等入射能量下中子轰击薄铁靶不同出射角度的次级中子双微分截面,并与实验数据进行对比。研究表明,在20 MeV以下能区,ENDF/B-VIII.0库的计算结果与实验数据符合较好,BROND-3.1、CENDL-3.1、JENDL-4.0u和JEFF-3.3库的计算结果与实验数据存在差异。在20~150 MeV能区,GEANT4程序的BERT模型和TALYS程序的计算结果与实验数据符合较好,INCLXX模型和BIC模型的计算结果与实验数据存在分歧。整体来看,需要对铁的中子评价数据和核反应理论模型做进一步研究。 相似文献
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随机中子动力学是核动力设计和核反应堆安全中的重要课题,本文从随机中子动力学的基础概念和研究方法出发,介绍随机中子动力学研究的历史发展和研究现状.裂变中子与光子的多重性是反应堆零功率中子噪声主要来源,对中子涨落的方程描述及其求解,演化出零功率中子噪声与功率反应堆噪声的随机理论.随机中子动力学的重要应用包括反应性微观测量、功率反应堆噪声测量和分析、核临界漂移分析和核材料识别与检测等.在半个多世纪的研究中,以脉冲堆点火过程的脉冲爆发等待时间分布为代表的随机性,一直缺乏定量分析方法和工具.直到近几年,模拟随机中子动力学过程的广义半马尔科夫过程模拟方法取得了重要进展,很好地揭示了脉冲堆实验中子点火规律.最后讨论随机中子动力学研究中有待解决的研究课题. 相似文献
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The prompt fission neutron spectra for the neutron-induced fission of 233U for low energy neutrons (below 6 MeV) are calculated using nuclear evaporation theory with a semi-empirical method, in which the partition of the total excitation energy between the fission fragments for the nth+233U fission reactions is determined by the available experimental and evaluation data. The calculated prompt fission neutron spectra agree well with the experimental data. The proportions of high-energy neutrons of prompt fission neutron spectrum versus incident neutron energies are investigated with the theoretical spectra, and the results are consistent with the systematics. The semi-empirical method could be a useful tool for the prompt evaluation of fission neutron spectra. 相似文献
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O. V. Zeynalova Sh. Zeynalov F. -J. Hambsch S. Oberstedt I. Fabry 《Bulletin of the Russian Academy of Sciences: Physics》2010,74(6):800-804
The emission of prompt fission neutrons in spontaneous fission of 252Cf was studied by the application of digital data processing for the first time. The study was aimed at comparing the obtained
results with those from the pioneering work of Budtz-Jorgensen and Knitter. By using a twin Frisch grid ionization chamber
for fission fragment detection and a neutron scintillator (NE213) for the detection of neutrons, a total of about 107 neutron coincidences were registered. The fission-fragment kinetic energies were measured using a fast (80 MHz) waveform
digitizer that provided 10-bit amplitude resolution. Standard analog NIM modules were used for neutron time-of-flight and
pulse shape measurements. A time-to-digital converter (TDC) with 1-ns resolution and a pair of gated charge-to-digital converters
with 12-bit amplitude resolution were also used. The fission fragment signals were analyzed by means of digital signal processing
algorithms. Data on prompt fission neutron energies were obtained by using a time-of-flight (TOF) spectrum unfolding procedure
applicable to list-mode data. 相似文献
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Low energy neutron induced fission of ~(235)U is studied in the framework of the multi-modal fission model. The fission fragment properties, such as the yields, the average total kinetic energy distribution and the average neutron separation energy, are investigated for incident neutron energies from thermal to 6.0 MeV. The multi-modal fission approach is also used to evaluate the prompt fission neutron multiplicity and spectra for the neutron-induced fission of ~(235)U with an improved version of the Los Alamos model for incident neutrons below the (n, nf) threshold. The three most dominant fission modes are taken into account. The model parameters are determined on the basis of experimental data. The calculated results are in good agreement with the experimental data. 相似文献
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M S Samant R P Anand R K Choudhury S S Kapoor K Kumar D M Nadkarni A Saxena 《Pramana》1993,40(4):299-309
The emission spectra of prompt fission neutrons from mass and kinetic energy selected fission fragments have been measured
in235U(n
th,f). Neutron energies were determined from the measurement of the neutron time of flight using a NE213 scintillation detector.
The fragment energies were measured by a pair of surface barrier detectors in one set of measurements and by a back-to-back
gridded ionization chamber in the second set of measurements. The data were analysed event by event to deduce neutron energy
in the rest frame of the emitting fragment for the determination of neutron emission spectra and multiplicities as a function
of the fragment mass and total kinetic energy. The results are compared with statistical model calculations using shell and
excitation energy dependent level density formulations to deduce the level density parameters of the neutron rich fragment
nuclei over a large range of fragment masses. 相似文献
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采用蒙特卡罗程序MCNP计算了西安脉冲堆中子代时间。使用MCNP程序模拟了反应堆瞬发中子通量密度衰减,基于忽略缓发中子项的点堆动力学方程计算出中子代时间。在微次临界下,研究了次临界度、源的分布、计数区域等对西安脉冲堆中子代时间计算结果的影响。计算分析表明:采用瞬发中子密度衰减法计算中子代时间时,微次临界度、源分布、计数区域等对计算结果影响都很小;误差产生的主要原因是忽略缓发中子项的点堆动力学方程并不能较好地反应瞬发中子通量密度的衰减规律。 相似文献
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Analysis of prompt fission neutron spectrum and multiplicity for 237Np(n,f) in the frame of multi-modal Los Alamos model 下载免费PDF全文
The improved version of Los Alamos model with the multi-modal fission approach is used to analyse the prompt fission neutron spectrum and multiplicity for the neutron-induced fission of 237Np. The spectra of neutrons emitted from fragments for the three most dominant fission modes (standard Ⅰ, standard Ⅱ and superlong) are calculated separately and the total spectrum is synthesized. The multi-modal parameters contained in the spectrum model are determined on the basis of experimental data of fission fragment mass distributions. The calculated total prompt fission neutron spectrum and multiplicity are better agreement with the experimental data than those obtained from the conventional treatment of the Los Alamos model. 相似文献