中子通量

A new flux expansion nodal method was developed to solve three-dimensional multigroup neutron diffusion equations in hexagonal-z geometry. The method expands the intranodal homogeneous flux distributions in analytic basis functions for each energy group.

提出了一种在三维六角形几何节块内数值求解多群中子扩散方程的节块法，该方法把节块内各群中子通量分布用解析基函数近似展开。

Finally, The way of how to measure the neutron flux distribution is made out.

最后介绍了次临界反应堆内中子通量密度数据的处理方法。

The design of the project design of the pulse neutron flux indicators over the world are running all the spallation neutron source.

项目设计中的脉冲中子通量设计指标，已经超过目前世界正在运行的所有散裂中子源。

of Absolute neutron flux measurement is presentedin this paper.

本文介绍了绝对中子通量测量方法，给出了各辐照腔典型位置上的绝对中子通量及其与全堆平均中子通量的比值。

According to the nonlinear dynamic model of a nuclear reactor , a new constant neutron flux density control method based on nonlinear state feedback is presented.

针对核反应堆点堆动态非线性模型，提出了一种非线性状态反馈的中子通量密度恒值控制的新方法。

Based on MCNP, authors developed the software package of the Monte Carlo method to simulate the neutron flux distributions with the space, energy and time for neutron logging.

作者在 MCNP的基础上，开发了中子测井，中子通量随空间、能量、时间分布蒙特卡罗模拟软件包。

The spatial distribution of intra-node flux and source were approximated by a new orthogonal quadratic polynomial expansion, and a second-order polynomial provided the spatial expansion of transverse-leakage. The neutron angular distribution of flux and transverse-leakage were represented by the S quadrature set.

节块内横向积分通量、中子源的空间分布使用新的正交二次多项式近似；横向泄漏项的空间分布使用二阶多项式近似；中子通量和横向泄漏的角度通过离散纵坐标S

A prediction model has been proposed to deal with threshold voltage shift as a function of 1MeV neutron flux and gate oxide thickness, and to deal with room-temperature annealing of threshold voltage shift induced-by 〓Coγ as a function of electric field and gate oxide thickness. The commonness and individuality of MOS device degradation between hot-carrier effect and ionizing radiation were investigated. The dependence of substrate current, gate current and threshold voltage shift due to hot-carrier on gate oxide thickness were simulated with MEDICI-2D simulator. The photocurrents of PN junction and bipolar transistor were studied. Their transient responses on varied bias voltages, pulse durations and absorbed doses were simulated. The influences of NPN base width on base and collector photocurrents were investigated. We also studied 1MeV neutron displacement damage in PN junction, and calculated reverse current leakage under the neutron flux of 2. 67×10〓 per square centimeter. 3 The study of nondestructive screening method for MOS radiation tolerance A theoretical and experimental study of nondestructive screening methods for radiation tolerance of nMOS and pMOS were firstly fulfilled. We determined the informative parameters pertinent to the method and proposed how to deal with experimental data and verify obtained results statistically, as well as make the required steps for nondestructive screening. Based on the experimental data of 180 samples of discrete pMOS devices, the relation between sample quantity and correlation coefficient, screening equation, and other significant results were obtained from the threshold voltage shifts of pre-and post-irradiation samples.

二、分立器件电离和位移辐射损伤响应研究在国内首次开展了电离辐射引起的氧化层阈值电压漂移和退火理论研究，编程计算了1MeV中子引起的MOS器件阈值电压漂移与中子通量及栅氧厚度的关系，计算了〓Coγ光子引起的阈值电压漂移及退火的时效曲线与纵向电场和栅氧厚度的关系等，对评估MOS型集成电路电离损伤和加固方法研究，以及论文中开展的MOSFETs无损筛选方法研究奠定了基础；分析了MOS器件热载流子损伤效应与辐射电离损伤效应之间的异同性，利用二维模拟软件MEDICI-2D模拟了衬底电流和栅电流，在不同栅氧厚度下随栅压的变化曲线，计算了热载流子效应造成的阈值电压漂移，研究结果对当前存在的以热载流子效应研究取代电离辐射损伤实验研究的设想，具有重要的参考价值；开展了PN结和双极晶体管电离光电流研究，计算了不同偏压、不同辐射脉宽和不同吸收剂量下PN结光电流的瞬时响应，计算了不同辐射脉宽下NPN晶体管基极电流和收集极电流的瞬时响应，以及基区宽度对NPN晶体管光电流的影响，研究结果对双极器件抗电离辐射损伤响应及加固方法研究具有重要意义；在国内首次开展了器件位移损伤的理论研究，分析了辐射产生的缺陷对电性能的影响，计算了注量为2.67×10〓cm〓的1MeV中子产生的缺陷对PN结反向电流的影响。

The accumulated self-exciting dose for Na-24 is only 1.12 mGy during its average life-time for irradiation of total thermal neutron fluence of 3.6E12 nth/cm^2. Conclusions: Because of the self-exciting dose reduced from neutron activation can be neglected for gamma dose measurement in neutron and gamma mixed field, and the threshold of linear response is 2 Gy, the FWT-70-40 dosimeter not only can be used for high dose rate Co-60 irradiation field and the high energy electron beam for medical purpose, but also can be used for gamma dose measurement in an epithermal neutron beam for boron neutron capture therapy.

型号FWT-70-4OM）剂量计於BNCT高中子通量与剂量的中子、加马混合辐射场所产生的自激剂量，对加马剂量度量干扰可忽略，且对加马的最低剂量限值为2Gy，因此除可应用於钴60加马高剂量辐射场与放射治疗用高能量、高剂量电子射束的剂量度量外，亦可应用於BNCT照射治疗用高能量、高剂量的中子、加马混合辐射场的加马剂量度量。

The neutron flux distributions are calculated from the 3D diffosion equations of two energy groups and six delayed neutron precursors by separaing the "time" and "space" variables.

堆芯中子通量分布采用分离变量法对两群六缓发中子组三维扩散方程来实时求解，并考虑慢化剂密度、硼浓度、氙和钐中毒、控制棒位置、燃料和慢化剂温度、燃料燃耗等因素对中子通量分布的影响。

The absorption and distribution of chromium were studied in ryeusing nutrient culture technique and pot experiment.

采用不同浓度K2CrO4(0，0.4，0.8和1.2 mmol/L)的Hoagland营养液处理黑麦幼苗，测定铬在黑麦体内的亚细胞分布、铬化学形态及不同部位的积累。

By analyzing theory foundation of mathematical morphology in the digital image processing, researching morphology arithmetic of the binary Image, discussing two basic forms for the least structure element: dilation and erosion.

通过分析数学形态学在图像中的理论基础，研究二值图像的形态分析算法，探讨最小结构元素的两种基本形态：膨胀和腐蚀；分析了数学形态学复杂算法的基本原理，把数学形态学的部分并行处理理念引入到家实际应用中。