期刊文献+
共找到705篇文章
< 1 2 36 >
每页显示 20 50 100
Measurement of ^(232)Th(n,2n)^(231)Th reaction cross-sections at neutron energies of 14.1 MeV and 14.8 MeV using neutron activation method 被引量:3
1
作者 兰长林 解保林 +2 位作者 张凯 彭猛 方开洪 《Nuclear Science and Techniques》 SCIE CAS CSCD 2015年第6期100-103,共4页
In this study, the activation cross-sections were measured for ^(232)Th(n,2n)^(231)Th reactions at neutron energies of 14.1 and 14.8 MeV, which were produced by a neutron generator through a T(d,n)~4He reaction. Induc... In this study, the activation cross-sections were measured for ^(232)Th(n,2n)^(231)Th reactions at neutron energies of 14.1 and 14.8 MeV, which were produced by a neutron generator through a T(d,n)~4He reaction. Induced gamma-ray activities were measured using a low background gamma ray spectrometer equipped with a high resolution HPGe detector. In the cross-section calculations, corrections were made regarding the effects of gamma-ray attenuation, dead-time, fluctuation of the neutron flux, and low energy neutrons. The measured cross-sections were compared with the literature data, evaluation data(ENDF-B/VII.1, JENDL-4.0 and CENDL-3.1), and the results of the model calculation(TALYS1.6). 展开更多
关键词 中子能量 反应截面 MEV 中子活化法 测量 HPGE探测器 中子发生器 高分辨率
下载PDF
Using activation method to measure neutron spectrum in an irradiation chamber of a research reactor 被引量:3
2
作者 周雪梅 刘桂民 +2 位作者 李达 王小鹤 孟令杰 《Nuclear Science and Techniques》 SCIE CAS CSCD 2014年第1期81-85,共5页
Neutron spectrum should be measured before test samples are irradiated.Neutron spectrum in an irradiation chamber of a research reactor was measured by using activation method when the reactor is in normal operation u... Neutron spectrum should be measured before test samples are irradiated.Neutron spectrum in an irradiation chamber of a research reactor was measured by using activation method when the reactor is in normal operation under 2 MW.Sixteen kinds of non-fission foils(19 reaction channels) were selected,of which 10 were sensitive to thermal and intermediate energy regions,while the others were of different threshold energy and sensitive to fast energy regions.By measuring the foil radioactivity,the neutron spectrum was unfolded with the iterative methods SAND-Ⅱ and MSIT.Finally,shielding corrections of group cross-section and main factors affecting the calculation accuracy were studied and the uncertainty of solution was analyzed using the Monte Carlo method in the process of SAND-Ⅱ. 展开更多
关键词 中子能谱 测量 辐照室 研究堆 活化法 阈值能量 蒙特卡罗方法 活化方法
下载PDF
Measurement of the prompt neutron spectrum from thermalneutron-induced fission in U-235 using the recoil proton method 被引量:2
3
作者 Tie He Pu Zheng Jun Xiao 《Nuclear Science and Techniques》 SCIE CAS CSCD 2019年第7期68-76,共9页
A measurement of the ^235U prompt fission neutron spectrum (PFNS) by the recoil proton method was performed at the Institute of Nuclear Physics and Chemistry, China. Details of the method, which include the calculatio... A measurement of the ^235U prompt fission neutron spectrum (PFNS) by the recoil proton method was performed at the Institute of Nuclear Physics and Chemistry, China. Details of the method, which include the calculation and validation of the response matrix, are presented. The PFNS for ^235U in the energy range 1–12 MeV, induced by thermal neutrons, was obtained. The measured spectrum in the low-energy region was in good agreement with previous work and the ENDF/B-VII library, except for minor differences. In the high-energy region, however, the relative height of the measured spectrum was greater, and an analysis of the experiment indicated uncertainties of 13% at 10 MeV and 24% at 12 MeV. Experimental results showed that the recoil proton method could be used to measure prompt fission neutron spectra. Some directions for future work are included. 展开更多
关键词 PROMPT FISSION neutron spectra RECOIL PROTON method Response matrix U-235
下载PDF
Spherical harmonics method for neutron transport equation based on unstructured-meshes 被引量:5
4
作者 CAOLiang-Zhi WU-Hong-Chun 《Nuclear Science and Techniques》 SCIE CAS CSCD 2004年第6期335-339,共5页
Based on a new second-order neutron transport equation, self-adjoint angular flux (SAAF) equation, the spherical harmonics (PN) method for neutron transport equation on unstructured-meshes is derived. The spherical ha... Based on a new second-order neutron transport equation, self-adjoint angular flux (SAAF) equation, the spherical harmonics (PN) method for neutron transport equation on unstructured-meshes is derived. The spherical harmonics function is used to expand the angular flux. A set of differential equations about the spatial variable, which are coupled with each other, can be obtained. They are solved iteratively by using the finite element method on un- structured-meshes. A two-dimension transport calculation program is coded according to the model. The numerical results of some benchmark problems demonstrate that this method can give high precision results and avoid the ray effect very well. 展开更多
关键词 有限元 中子传输方程 球形谐函数 无结构网 偏微分方程
下载PDF
Neutron excess method for performance assessment of thoriumbased fuel in a breed-and-burn reactor with various coolants 被引量:4
5
作者 Kun Yang Wei Qin +1 位作者 Jin-Gen Chen Xiang-Zhou Cai 《Nuclear Science and Techniques》 SCIE CAS CSCD 2016年第4期167-173,共7页
Fertile fuel, such as thorium or depleted uranium, can be bred into fissile fuel and burnt in a breed-andburn(B&B) reactor. Modeling a full core with fertile fuel can assess the performance of a B&B reactor wi... Fertile fuel, such as thorium or depleted uranium, can be bred into fissile fuel and burnt in a breed-andburn(B&B) reactor. Modeling a full core with fertile fuel can assess the performance of a B&B reactor with exact quantitative estimates, but costs too much computation time. For simplicity, performing the recently developed neutron balance method with a zero-dimensional(0-D)model can also provide a reasonable result. Based on the0-D model, the feasibility of the B&B mode for thorium fuel in a fast reactor cooled by sodium was investigated by considering the(n, 2n) and(n, 3n) reaction rates of fuel and coolant in this work, and compared with that of depleted uranium fuel. Afterward, the performance of the same thorium-based fuel core, but cooled by helium, lead-bismuth, and FLi Be, respectively, is discussed. It is found that the(n, 2n) and(n, 3n) reactions should not be neglected for the neutron balance calculation for thorium-based fuel to sustain the B&B mode of operation. 展开更多
关键词 性能评估 钠燃料 冷却剂 反应器 中子 燃烧 零维模型 化学反应速率
下载PDF
Unfolding the measured neutron spectra in the irradiation chamber of the UZrH reactor using iterative method
6
作者 LIU Shuhuan CHEN Da +3 位作者 LIU Nannan A Jingye ZHANG Wenshou WANG Kai 《Nuclear Science and Techniques》 SCIE CAS CSCD 2007年第2期77-81,共5页
In the procedure of neutron fluence measurement in the whole energy range (10-4 eV^18 MeV), in the irra- diation chamber of a UZrH reactor, the neutron energy spectra are unfolded using the method of minimizing direct... In the procedure of neutron fluence measurement in the whole energy range (10-4 eV^18 MeV), in the irra- diation chamber of a UZrH reactor, the neutron energy spectra are unfolded using the method of minimizing directed divergence and SAND-II, which are used broadly at home and abroad. These methods belong to the iterative methods. In this article, the procedure of the spectra unfolding using the two methods is described in detail. The neutron spec- trum distribution unfolded by the two methods agree well with each other. In the end, the major differences of the two iterative methods are compared with each other, and the main factors affecting the accuracy of the spectra unfolding with the iterative method are discussed. 展开更多
关键词 UZrH反应堆 辐照腔 迭代法 测量 中子谱
下载PDF
TRACING METHOD OF NATURAL SEDIMENTS BY NEUTRON ACTIVATION
7
作者 茅志祥 严佩岚 +6 位作者 黄建维 戴贤凯 韩乃斌 柴之芳 钱琴芳 马淑兰 马建国 《Nuclear Science and Techniques》 SCIE CAS CSCD 1991年第2期121-128,共8页
A new method of NAA for sediment movement study is presented in this paper. Through analyzing the natural sediment, the information about natural tracing agents has been obtained, which can show the direction of sedim... A new method of NAA for sediment movement study is presented in this paper. Through analyzing the natural sediment, the information about natural tracing agents has been obtained, which can show the direction of sediment movement and relative discharge of sediment transportation. Test results in some areas, such as Shantou Harbour and Hangzhou Bay, are in good agreement with those from normal hydrologic measurements and some results are not obtainable with the latter. The NAA is economical, practical and reliable, and should be widely used in engineering practice. 展开更多
关键词 TRACING method NATURAL SEDIMENT neutron activation NAA
下载PDF
Neutron activation method in the analysis of environmental objects
8
作者 G.M. Kolesov(V.I.Vernadsky Institute of Geochem。&Anal.Chem.,Russian Academy of effciences,Kosygin St.19,Moskow,Russian) 《Journal of Environmental Sciences》 SCIE EI CAS CSCD 1995年第1期92-100,共9页
NeutronactivationmethodintheanalysisofenvironmentalobjectsG.M.Kolesov(V.I.VernadskyInstituteofGeochem。&Anal.... NeutronactivationmethodintheanalysisofenvironmentalobjectsG.M.Kolesov(V.I.VernadskyInstituteofGeochem。&Anal.Chem.,RussianAcad... 展开更多
关键词 neutron activation analysis:environmental objects nuclear-physical methods.
下载PDF
Computing Differentially Rotating Neutron Stars Obeying Realistic Equations of State by Using Hartle’s Perturbation Method
9
作者 Anastasios Katelouzos Vassilis Geroyannis 《International Journal of Astronomy and Astrophysics》 2013年第3期217-226,共10页
In this paper, we use the well-known Hartle’s perturbation method in order to compute models of differentially rotating neutron stars obeying realistic equations of state. In our numerical treatment, we keep terms up... In this paper, we use the well-known Hartle’s perturbation method in order to compute models of differentially rotating neutron stars obeying realistic equations of state. In our numerical treatment, we keep terms up to third order in the angular velocity. We present indicative numerical results for models satisfying a particular differential rotation law. We emphasize on computing the change in mass owing to this differential rotation law. 展开更多
关键词 Change in Mass Differential Rotation General-Relativistic Models neutron Stars Numerical methods REALISTIC Equations of State
下载PDF
A SPECTRAL STREAMLINE DIFFUSION FINITE ELEMENT COUPLING METHOD OF UNSTEADY TRANSPORT EQUATION IN THE FIELD OF NEUTRON LOGGING
10
作者 梅立泉 《Applied Mathematics and Mechanics(English Edition)》 SCIE EI 1999年第7期38-46,共9页
In this paper, a new numerical method, the coupling method of spherical harmonic function spectral and streamline diffusion finite element for unsteady Boltzmann equation in the neutron logging field, is discussed. Th... In this paper, a new numerical method, the coupling method of spherical harmonic function spectral and streamline diffusion finite element for unsteady Boltzmann equation in the neutron logging field, is discussed. The convergence and error estimations of this scheme are proved. Its applications in the field of neutron logging show its effectiveness. 展开更多
关键词 neutron logging transport equation finite element method streamline diffusion
下载PDF
Calculation of Neutron-Proton Mass Difference by the Monte Carlo Method
11
作者 A. A. Sobko S. A. Garelina 《Journal of Applied Mathematics and Physics》 2020年第10期2157-2166,共10页
Calculation results of the Monte Carlo method of the average energy of the electrostatic interaction between the quarks are presented to the neutron and proton. The proposed model of the distribution of quarks in prot... Calculation results of the Monte Carlo method of the average energy of the electrostatic interaction between the quarks are presented to the neutron and proton. The proposed model of the distribution of quarks in protons and neutrons is possible to assess the area which included a strong (gluon) interaction. Given the fact that the probability of finding a quark in the field with strong interaction is less than one, there is a good agreement between the experimental and calculated values of the mass difference between the neutron and the proton. 展开更多
关键词 Mass of the Proton The neutron Mass The Coulomb Interaction The Monte Carlo method
下载PDF
医院中子照射器治疗束中子参数测量
12
作者 石斌 张书峰 +9 位作者 陈军 刘显科 肖鸿飞 张紫竹 屈渤添 王倩 曹平 张庆贤 宋明哲 刘蕴韬 《同位素》 CAS 2024年第1期1-6,共6页
为了对医院中子照射器的设计指标进行验证,利用金箔活化法测量了其治疗束出口处中子注量率,并采用金刚石探测单元的扫描装置测量治疗束出口处热中子、超热中子、快中子和γ射线注量率的径向分布。结果显示,在30 kW满功率运行时,热中子... 为了对医院中子照射器的设计指标进行验证,利用金箔活化法测量了其治疗束出口处中子注量率,并采用金刚石探测单元的扫描装置测量治疗束出口处热中子、超热中子、快中子和γ射线注量率的径向分布。结果显示,在30 kW满功率运行时,热中子束及超热中子束出口中心处,热中子注量率分别为1.75×10^(9)cm^(-2)·s^(-1)和6.57×10^(7)cm^(-2)·s^(-1),超热中子注量率分别为1.41×10^(7)cm^(-2)·s^(-1)和3.14×10^(8)cm^(-2)·s^(-1);治疗束主要分布在束流孔径内,靠近束流边缘会出现指数级下降现象。该测量结果为医院中子照射器开展后续相关测试及实验提供了参数支持。 展开更多
关键词 热中子注量率 硼中子俘获治疗 活化法 径向分布
下载PDF
用于反应堆启动的Am-Be中子源物理特性研究
13
作者 王帅 吴师其 +1 位作者 李满仓 周代杰 《现代应用物理》 2024年第1期66-70,共5页
利用蒙特卡罗程序对采用合金法制备的Am-Be中子源辐照前中子源强能谱、伴生γ放射性等物理特性及其在堆内辐照过程中的变化情况进行了分析,评估了其作为压水型核电反应堆启动中子源的可行性。分析表明:合金法制作的单个Am-Be中子源(源... 利用蒙特卡罗程序对采用合金法制备的Am-Be中子源辐照前中子源强能谱、伴生γ放射性等物理特性及其在堆内辐照过程中的变化情况进行了分析,评估了其作为压水型核电反应堆启动中子源的可行性。分析表明:合金法制作的单个Am-Be中子源(源活性区尺寸φ3.4 mm×236 mm,密度为4 g·cm^(-3))中子发射率可达3.34×10^(7)s^(-1),该源的源强虽低于核电厂反应堆常用的启动中子源,但多个Am-Be中子源叠加也可满足应用要求。Am-Be中子源在堆芯辐照过程中,由于产生的^(242)Cm等核素的影响,总中子源强高于其初始源强,保证其长期起到启动中子源作用。另外,Am-Be中子源具有较高的γ源强,在制造、运输与安装过程中需要考虑辐射防护问题。 展开更多
关键词 Am-Be中子源 反应堆启动 合金法
下载PDF
能群独立的中子输运非结构网格自适应加密
14
作者 郭海兵 阮政霖 马纪敏 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第7期1495-1504,共10页
为兼顾中子输运的模拟精度和计算效率,对网格进行自适应加密和区域分解并行是有效技术途径。通常各能群的中子通量密度分布有较大差异,采用统一的网格不能最佳匹配各群通量密度的空间变化,只能全局加密网格或损失精度。本文通过对各能... 为兼顾中子输运的模拟精度和计算效率,对网格进行自适应加密和区域分解并行是有效技术途径。通常各能群的中子通量密度分布有较大差异,采用统一的网格不能最佳匹配各群通量密度的空间变化,只能全局加密网格或损失精度。本文通过对各能群中子通量密度分别进行后验误差估计,开展能群独立的局部网格加密,获得与各能群的中子通量密度分别匹配的多组非结构网格,即基于共同父网格(粗网格)的多组独立子网格(细网格),进而开发了在这种层次化父-子网格上的多群中子输运模拟耦合算法,通过连续的多轮次自适应加密,实现了不受初始网格分辨率影响的高精度、高效率求解。基于该网格方法建立了间断有限元输运程序ENTER-Ⅱ,并借助开源算法库DEAL.Ⅱ实现了区域分解并行。初步验证表明,计算结果符合良好,时间效率有明显提升。 展开更多
关键词 中子输运 间断有限元 非结构网格 自适应加密 父-子网格 区域分解
下载PDF
铼的中子辐射俘获反应截面测量
15
作者 王晓宇 贺国珠 +13 位作者 张奇玮 罗淏天 徐阔之 李倩 解立坤 栾广源 阮锡超 邹翀 陈玄博 吴鸿毅 樊瑞睿 蒋伟 曹平 余滔 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第11期2262-2268,共7页
铼及铼钼合金是空间堆建造中的重要结构材料,其高精度的中子辐射俘获反应截面等数据在空间堆设计中具有重要意义。利用γ射线全吸收型BaF2探测装置(GTAF)和瞬发γ射线在线测量方法,在中国散裂中子源(CSNS)的反角白光中子束线(Back-n)上... 铼及铼钼合金是空间堆建造中的重要结构材料,其高精度的中子辐射俘获反应截面等数据在空间堆设计中具有重要意义。利用γ射线全吸收型BaF2探测装置(GTAF)和瞬发γ射线在线测量方法,在中国散裂中子源(CSNS)的反角白光中子束线(Back-n)上,在线测量了铼的两个同位素样品^(185)Re和^(187)Re的中子辐射俘获反应截面。初步得到了^(185)Re和^(187)Re在0.5 eV~10 keV能区中子辐射俘获反应的激发函数,并将^(185)Re(n,γ)^(186)Re和^(187)Re(n,γ)188Re的激发函数实验数据与ENDF/B-Ⅷ.0数据库中的评价曲线进行比对分析,实验数据与评价曲线在可分辨共振峰处基本一致,进一步印证了评价曲线,也为在CSNS白光中子源开展更高精度的中子辐射俘获反应截面测量提供支持,为空间堆物理研究提供数据基础。 展开更多
关键词 瞬发γ射线测量方法 (n γ)反应
下载PDF
基于隐式重启Arnoldi方法的中子扩散本征值问题求解及其降阶研究 被引量:1
16
作者 向钊才 陈洽锋 +1 位作者 赵鹏程 张庆航 《核技术》 EI CAS CSCD 北大核心 2024年第2期135-141,共7页
中子扩散方程高阶谐波可用于重构堆芯中子注量率分布,但传统源迭代与源修正迭代法求解时的收敛速度慢,计算耗时长。采用隐式重启Arnoldi方法(Implicitly Restarted Arnoldi Method,IRAM)求解本征值问题的中子扩散方程获得谐波数据,通过... 中子扩散方程高阶谐波可用于重构堆芯中子注量率分布,但传统源迭代与源修正迭代法求解时的收敛速度慢,计算耗时长。采用隐式重启Arnoldi方法(Implicitly Restarted Arnoldi Method,IRAM)求解本征值问题的中子扩散方程获得谐波数据,通过本征正交分解(Proper Orthogonal Decomposition,POD)与伽辽金(Galerkin)投影相结合的方法构建POD-Galerkin低阶模型,并重构二维稳态TWIGL基准题中子注量率分布。研究结果表明:IRAM方法在求解中子扩散方程的高阶本征值和谐波问题上具有较高的精度;基于POD-Galerkin低阶模型重构中子注量率分布具有较高的保真性与计算效率,有效增值系数与参考解的误差为8.7×10^(-5),对角线上快群和热群中子注量率最大相对误差为2.56%,且低阶模型计算用时仅为全阶模型的10.18%。本研究为堆芯中子注量率重构提供了一种可靠且高效的方法,该方法不仅可用于重构稳态时堆芯中子注量率分布,还具有在瞬态情况下预测中子注量率分布的潜力,有望在未来的应用中进一步拓展。 展开更多
关键词 中子扩散方程 隐式重启Arnoldi方法 本征正交分解 伽辽金投影 中子注量率重构
下载PDF
稳态及瞬态中子输运模型的JFNK求解方法研究 被引量:1
17
作者 张杨奕 张天铖 周夏峰 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第6期1234-1241,共8页
三维全堆芯pin-by-pin中子输运模型的高效加速方法是核反应堆高精度计算的重点和难点。本文有效融合课题组开发的并行多维离散纵坐标(S_(N))中子输运程序comeSn和Jacobian-Free Newton Krylov(JFNK)通用求解框架comeJFNK的高效并行特性... 三维全堆芯pin-by-pin中子输运模型的高效加速方法是核反应堆高精度计算的重点和难点。本文有效融合课题组开发的并行多维离散纵坐标(S_(N))中子输运程序comeSn和Jacobian-Free Newton Krylov(JFNK)通用求解框架comeJFNK的高效并行特性、鲁棒性和强收敛性,开发了一套三维稳态及瞬态中子输运模型的JFNK并行求解程序comeSn_JFNK。为了提高计算效率,选择中子标通量密度(而非中子角通量密度)作为JFNK全局求解变量,并利用基于空间区域并行的KBA输运扫描方法和物理预处理方法,分别构建了稳态及瞬态模型的JFNK统一残差计算模型。计算结果表明,comeSn_JFNK相比于comeSn,计算效率具有显著优势,对于三维pin-by-pin稳态KAIST-3A算例,加速比为10倍以上;对于栅元均匀化的二维七群瞬态C5G7-TD2系列基准算例,加速比约为30倍。 展开更多
关键词 JFNK方法 中子输运模型 离散纵坐标法 稳态和瞬态
下载PDF
基于半经验法多球中子谱仪校准
18
作者 孙博文 曾志 +2 位作者 张辉 马豪 李君利 《辐射防护》 CAS CSCD 北大核心 2024年第2期120-125,共6页
基于半经验法扣除中子散射本底,提出了一种多球中子谱仪校准的新方法。首先用热中子参考辐射装置校准多球中子谱仪各中子球内He-3正比计数器的探测效率。用多球中子谱仪各中子球单独测量参考^(241)Am-Be中子源,结合半经验法扣除散射,给... 基于半经验法扣除中子散射本底,提出了一种多球中子谱仪校准的新方法。首先用热中子参考辐射装置校准多球中子谱仪各中子球内He-3正比计数器的探测效率。用多球中子谱仪各中子球单独测量参考^(241)Am-Be中子源,结合半经验法扣除散射,给出了各中子球的注量响应。结合两者实验结果,获得^(241)Am-Be源能谱并给出谱仪注量响应。结果表明,校准的多球中子谱仪具备快中子区测量能力。 展开更多
关键词 多球中子谱仪 校准 中子能谱 半经验法
下载PDF
三维球床几何稀疏条数长特征线加速方法
19
作者 郭建 郭炯 +2 位作者 李富 严睿 邹杨 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第3期654-661,共8页
特征线法具有非常强的几何适应性,可用于三维球床高温气冷堆全堆芯求解,但存在迭代次数多、计算速度慢的缺点。本文将长特征线加速方法应用于三维球床高温气冷堆以解决非规则几何数值加速的问题,基于三维模型特征线布置较二维模型稠密... 特征线法具有非常强的几何适应性,可用于三维球床高温气冷堆全堆芯求解,但存在迭代次数多、计算速度慢的缺点。本文将长特征线加速方法应用于三维球床高温气冷堆以解决非规则几何数值加速的问题,基于三维模型特征线布置较二维模型稠密的分析,提出了稀疏条数长特征线加速方法,极大地减少了加速方程的计算量,在不降低角度离散精度的前提下,获得了非常好的加速效果。通过基准题对加速参数的选取方式进行了研究,条数稀疏度取3~5、长特征线长度取2.0 cm左右、加速迭代步取20~60步可获得良好的加速效果。小型轻水堆三维基准题和球床堆芯简化模型的计算结果表明,采用稀疏条数长特征线加速可获得7倍左右的时间加速比,此时对应的迭代步加速比为20倍左右。 展开更多
关键词 球床高温气冷堆 特征线法 长特征线加速方法 中子输运
下载PDF
无源中子符合计数法测量MOX中钚质量铀干扰修正方法研究
20
作者 张俞奇 许小明 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第6期1372-1379,共8页
无源中子符合计数法可以在不破坏MOX(mixed oxide)燃料的前提下,测量其中子信号进行符合分析而得出Pu含量,但在MOX燃料的测量应用过程中,Pu自发裂变中子会诱发U产生显著诱发中子信号,对于Pu的测量产生干扰。通过蒙特卡罗模拟与MSR数据... 无源中子符合计数法可以在不破坏MOX(mixed oxide)燃料的前提下,测量其中子信号进行符合分析而得出Pu含量,但在MOX燃料的测量应用过程中,Pu自发裂变中子会诱发U产生显著诱发中子信号,对于Pu的测量产生干扰。通过蒙特卡罗模拟与MSR数据处理方法,开展了无源中子符合计数法测量MOX燃料中Pu质量时U产生的诱发中子信号干扰比例模拟研究。模拟结果分别给出了U诱发信号干扰占比随MOX燃料样品PuO_(2)质量含量、密度、质量的变化关系,得到了明确的函数关系式。该方法适用于样品密度在1.5~9.0 g/cm^(3)、质量在10~500 g、PuO_(2)含量在1%~44%范围的MOX燃料无源中子符合计数法测量的修正,修正因子为0.64%~8.49%,适用于快堆及热堆以及不同生产阶段MOX燃料中U、Pu含量的测量分析。 展开更多
关键词 MOX 蒙特卡罗模拟 无源中子符合计数法
下载PDF
上一页 1 2 36 下一页 到第
使用帮助 返回顶部