共查询到20条相似文献,搜索用时 31 毫秒
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Hideo Harada Atsushi Kimura Fumito Kitatani Mitsuo Koizumi Harufumi Tsuchiya Bjorn Becker 《Journal of Nuclear Science and Technology》2013,50(6):837-843
Neutron resonance densitometry (NRD) is a non-destructive analysis method, which can be applied to quantify special nuclear materials (SNM) in small particle-like debris of melted fuel that are formed in severe accidents of nuclear reactors such as the Fukushima Daiichi nuclear power plants. NRD uses neutron resonance transmission analysis (NRTA) to quantify SNM and neutron resonance capture analysis (NRCA) to identify matrix materials and impurities. To apply NRD for the characterization of arbitrary-shaped thick materials, a generalized method for the analysis of NRTA data has been developed. The method has been applied on data resulting from transmission through thick samples with an irregular shape and an areal density of SNM up to 0.253 at/b (≈100 g/cm2). The investigation shows that NRD can be used to quantify SNM with a high accuracy not only in inhomogeneous samples made of particle-like debris but also in samples made of large rocks with an irregular shape by applying the generalized analysis method for NRTA. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(9):1131-1141
New evaluation of neutron-induced nuclear data for five stable isotopes of zinc (mass numbers A = 64, 66, 67, 68, and 70) was consistently carried out in the incident neutron energy range from 10?5 eV up to 20MeV. In the low energy region up to about 100keV, the resonance parameters were evaluated by taking account of the available measured data. In the fast neutron region, the comprehensive calculations with nuclear reaction models, in which compound, preequilibrium, and direct processes are taken into account, were performed to estimate cross sections for various reactions and double differential cross sections of emitted neutrons and γ-rays. The comparisons of the evaluated cross sections with the experimental data and existing evaluated nuclear data libraries are made and show a good agreement with the measurements. 相似文献
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In order to achieve the goal of nuclear security, the neutron generator is used to image shielded nuclear material by non-destructive analysis method. In order to improve the imaging quality, it is necessary to collimate the slowed neutrons. In this paper, the Monte Carlo software Geant4 was used to theoretically model a new compact thermal neutron collimator based on gadolinium-doped silicate, and the thermal neutron transmittance and collimation ratio of the collimator were simulated and calculated. The calculation results will be used to guide the subsequent construction of neutron-based nuclear material imaging systems. 相似文献
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中子辐射俘获截面及共振参数在核工程设计、核天体物理等研究领域中有重要的应用价值。在中国散裂中子源(CSNS)反角白光中子束线(Back n)上,使用C6D6测量系统开展了169Tm辐射俘获反应测量。通过脉冲高度权重技术、共振吸收法和饱和归一法得到169Tm辐射俘获反应的产额。利用SAMMY程序拟合169Tm的产额数据,得到169Tm在1~100 eV能量区间的共振能量、中子宽度、辐射俘获宽度等共振参数。使用实验测得的共振参数和Reich Moore近似计算了169Tm在1~100 eV能量区间的辐射俘获截面。实验测量结果与ENDF/B Ⅷ.0数据库的推荐值总体符合较好,部分共振参数和截面存在一定的差异。产生这些差异的原因与Back n的源中子能谱结构、能量分辨率、实验本底的精度有关。 相似文献
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本文开发了自主化的核数据处理程序NECP-Atlas,该程序将不同的核数据处理功能封装为不同的程序模块,可将评价核数据经过共振重构及线性化、多普勒展宽计算、不可分辨共振区处理、热中子散射计算、多群截面计算等过程,处理为WIMS-D/E格式多群数据库。采用WLUP(WIMSD library update project)基准题、国际临界安全基准题ICSBEP(international criticality safety benchmark evaluation project)等对NECP-Atlas加工产生的核数据进行验证,结果显示NECP-Atlas和NJOY-2016程序精度相当。 相似文献
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本工作优化设计建立了1套可用于核保障中核材料衡算的液体闪烁体中子多重性测量装置,并基于该装置开展了性能测试。结果表明,装置运行状态稳定,各项指标均在可接受范围内。同时开展了对252Cf源和标准Pu样品的实验室模拟测量等中子多重性测量研究。结果表明,该测量装置的探测效率好于15%,测量相对标准偏差为8.6%,表明在条件允许时,通过长时间信号采集,该中子多重性测量装置有能力替代基于3He管的中子多重性测量装置,通过中子多重性分析完成核保障中核材料衡算定量测量任务。 相似文献
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先进裂变核能的关键核数据测量和CSNS白光中子源 总被引:1,自引:1,他引:0
在设计加速器驱动的次临界系统(ADS)、核废料嬗变装置及钍基熔盐堆时亟需一些关键核数据,当前核数据库受实验条件或中子能区的限制,存在核数据精度不高甚至少部分核素数据缺失的情况。本文综述了国内外相关的核数据研究和相应的白光中子源情况。基于中国散裂中子源(CSNS)的反角通道白光中子源实验终端的中子束流具有非常宽的能谱(0.01 eV~200 MeV)和很好的时间特性。模拟得到距靶80 m处的实验终端的中子注量率为9.3×106cm-2•s-1,1 eV ~ 1 MeV能量间隔内的中子数占总中子数的53%;同时,加速器运行在双束团模式或单束团模式,时间分辨率均在0.3%~0.9%之间,适合开展核数据测量。 相似文献
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Keiichi Shibata 《Journal of Nuclear Science and Technology》2016,53(7):957-967
Neutron nuclear data on four isotopes of tantalum have been evaluated for the next version of Japanese Evaluated Nuclear Data Library general-purpose file in the energy region from 10?5 eV to 20 MeV. Unresolved resonance parameters were obtained by fitting to the total and capture cross sections calculated from nuclear models, while resolved resonance parameters were selected from experimental data. A statistical model code was applied to evaluate cross sections above the resolved resonance region. Compound, pre-equilibrium and direct-reaction processes were considered for cross-section calculation. Coupled-channel optical-model parameters were employed for the interaction between neutrons and nuclei. Giant-dipole and pygmy resonance parameters for E1 γ-ray transition from tantalum isotopes were determined so as to reproduce measured γ-ray spectrum for 181Ta. The present results reproduce experimental data very well. The evaluated data are compiled into Evaluated Nuclear Data File (ENDF) formatted data files. 相似文献
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利用中子共振谱技术可以克服光学和热电偶测温技术的限制,得到封闭系统内部的温度分布.很多金属元素都具有典型的中子共振吸收曲线,且其共振曲线随着中子-靶核的运动能量增加而展宽,而系统能量与温度成比例关系.中子共振谱测温系统通常由中子源、中子能谱探测与分析系统以及屏蔽系统等构成.由于中子对大多数材料具有很强的穿透性,中子共振谱测温技术可以在炸药爆轰、冲击波研究等动态系统的研究领域中发挥重要作用. 相似文献
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基于中国原子能科学研究院的中子学积分实验装置,利用BC501A液体闪烁体探测器,结合飞行时间法(TOF)测量了镓样品的泄漏中子谱。采用MCNP 4C程序进行了模拟并与实验泄漏中子谱进行了比较,对ENDF/B-Ⅶ.1、JEFF-3.2、TENDL-2015数据库中镓核中子评价数据进行了宏观基准检验分析,并与TALYS程序计算结果作对比。研究结果显示:在9 MeV以下能区,TENDL-2015库与实验结果符合很好;在弹性散射能区,JEFF-3.2和TENDL-2015库与实验结果符合较好;对于12 MeV左右的非弹性散射峰,JEFF-3.2库与实验结果符合较好,TALYS计算结果显示该部分主要来自镓核分离能级的贡献。 相似文献
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为研究国产中子气泡探测器在核测井中子个人剂量监测中的适用性,采用国内研制的中子气泡探测器对核测井运源车外表面、车内兼用储源仓周围等关注点的中子辐射水平进行监测,同时采用进口LB6411型中子周围剂量当量仪进行比对监测。实验结果表明,当运源车兼用储源仓内仅装载中子源时,中子气泡探测器与LB6411的测量结果无显著统计学差异,两者测量结果符合较好,中子气泡探测器的测量结果准确可信;当兼用储源仓分别装载中子源、中子-γ源时,两组中子气泡探测器的测量结果也无显著统计学差异,中子气泡探测器适用于中子-γ混合辐射场中子辐射剂量的测量。中子气泡探测器在运源车现场与在241Am-Be源标准中子场中的剂量响应灵敏度因子间的相对偏差为7.4%,验证了其较好的能量响应特性,并显示了在核测井现场条件下用于中子个人剂量监测的适用性。 相似文献
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研究了中子弹核爆炸剩余核辐射估算的数学模型,给出了地面放射性沾染、通过和停留剂量估算的数学模型。 相似文献
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研究了中子弹核爆炸早期核辐射效应估算的数学模型,给出了中子注量、中子个人吸收剂量、中子周围吸收剂量、γ辐射周围吸收剂量、γ辐射个人吸收剂量以及早期核辐射总的个人剂量估算的数学模型. 相似文献
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散裂中子源与先进核能系统 总被引:1,自引:0,他引:1
LI SHOUNAN 《核科学与工程》1998,(1)
散裂中子源的应用日益受到人们的重视。本报告仅对散裂中子源的历史、物理基础、对加速器要求、靶系统及其应用于先进核能系统作一般介绍。 相似文献
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