瞬发中子密度衰减法计算中子代时间

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。     

高温反应堆瞬发中子代时间计算

高温核反应堆在磁流体发电和核火箭等领域有良好的应用前景。高温反应堆具有堆芯温度高、结构复杂等特点,其中子物理性能参数的计算难度较大。研究了高温核反应堆瞬发中子代时间的计算方法,介绍了多种方法的计算原理和一种新型高温核反应堆的计算结果。研究表明,对于相同的反应堆模型,几种方法的计算结果符合较好,计算结果可信。     

高温反应堆瞬发中子代时间计算

高温核反应堆在磁流体发电和核火箭等领域有良好的应用前景。高温反应堆具有堆芯温度高、结构复杂等特点,其中子物理性能参数的计算难度较大。研究了高温核反应堆瞬发中子代时间的计算方法,介绍了多种方法的计算原理和一种新型高温核反应堆的计算结果。研究表明,对于相同的反应堆模型,几种方法的计算结果符合较好,计算结果可信。     

裂变瞬发中子多重性研究

本文介绍了裂变瞬发中子多重性这一研究领域的概况，着重介绍获第二届吴有训物理奖的“自发裂变和中子诱发裂变的瞬发中子多重性的研究”成果的主要内容和意义．     

2.8MeV中子诱发238U裂变的瞬发中子谱高能段实验测量

在中国原子能科学研究院的高压倍加器上利用中子飞行时间方法测量了2.8 MeV中子引起238U裂变的瞬发中子能谱,通过增大样品量和设计合适的屏蔽体提高了效应/本底比,使得测量数据的不确定度满足预期目标（在5.5～14 MeV能区内,能量间隔为0.5 MeV条件下能谱的不确定度小于10%）。将实验几何、中子源能量分布及角分布、探测效率、束流的时间结构等实验条件输入到MCNP程序里,模拟了出射的中子谱,模拟结果与测量结果在不确定度范围内一致,验证了在入射中子能量较低时238>U的裂变瞬发中子谱评价数据的可靠性。The Prompt Fission Neutron Spectrum (PFNS) of 238U induced by 2.8 MeV neutron was measured using the Cockcroft-Walton accelerator in China Institute of Atomic Energy (CIAE). The signal/background ratio was improved by increasing the amount of sample mass and using an appropriate shielding system. The final uncertainty of neutron energy spectrum in 5.5～14 MeV region is less than 10% with a bin size of 0.5 MeV which has reached this project's anticipation. The experimental geometry, the angular distribution and energy distribution of neutron source, the detection efficiency and time structure of deuteron beam were inputted into the MCNP code to simulate the outgoing neutron spectrum. The simulated results agree with the experimental ones within the uncertainty. The result indicates that the evaluated PFNS for 238U at low neutron energy is reliable.     

瞬发中子衰减常数的脉冲中子源法测量系统建立

在向没有任何缓发中子先驱核存在的次临界系统中注入一束脉冲中子后，系统中的瞬发中子强度随空间和能量分布的形状在经过很短一段时间的调整后，将A=Aoexp(λ，t）衰减，A为瞬发中子强度，s^-1；A0为初始瞬发中子强度，s^-1；t为瞬发中子衰减时间，s；λ为瞬发中子衰减常数，s^-1。     

中子俘获瞬发γ活化分析数据库

简要地介绍了热中子俘获瞬发γ射线数据的测量、评价、检验及其中子俘获瞬发γ射线活化分析数据库的研制、结构和基本数据内容等. The evaluation, measurement, and check of prompt γ-ray data for neutron capture are presented. The development of the database of prompt γ-ray activation analysis for neutron capture, and its structure and basical data are also described in the text.     

瞬发γ活化分析系统的建立

瞬发γ中子活化分析是重要的核分析方法之一,是H和B等轻元素的重要分析手段,近年来应用范围不断增加.概要介绍了瞬发γ中子活化分析的基本原理,重点介绍了中国原子能科学研究院重水研究堆热中子束瞬发γ中子活化分析实验装置以及50 keV－11 MeV的宽能区γ效率刻度方法.还应用瞬发γ中子活化分析分析了海底锰结核标准物质GSPN 3中11种元素,结果与标准值基本一致.Neutron induced prompt γ activation analysis(PGNAA),is one of the nuclear analytical method,which is a powerful tool for H,B,etc.undestructive determination.The applications of PGNAA are increased in recent years.In this paper,the basic principle of PGNAA was introduced briefly.The facilities of PGNAA in HWRR of China Institute of Atomic Energy as well as the efficiency calibration for a wide range gamma from 50 keV to 10 MeV were emphasized.A deep sea polymetallic nodule CRM,GSPN 3 was analyzed by using PGNAA in this work,the results have agreement with the certified values.     

基于瞬发伽马中子活化分析技术的金属样品检测研究

在合金材料的生产过程中,不同金属元素的含量改变对产品的性能以及可靠性有重要的影响,通过在线检测技术能够对产品中不同元素含量进行实时分析,从而指导其工业生产过程,提高产品质量。目前常规的无损检测方法受限于分析深度,无法对样品内部成分进行分析,从而影响测量结果的准确性。瞬发伽马中子活化分析（PGNAA）技术是一种高灵敏度、多元素同时分析的无损检测技术,可以对大块样品进行快速分析。针对PGNAA技术在大体积金属样品检测的可行性进行研究,通过测量快中子与样品发生非弹性散射反应激发的伽马射线对样品成分进行分析。搭建了一套测量系统,包括D-T中子发生器,中子反射体,中子准直体,高纯锗（HPGe）探测器及探测器屏蔽防护。首先,对Fe,Ti,Cr,Ni和Cu等5种金属元素进行了分析研究。对不同质量下的样品进行测量,通过伽马能谱处理软件GAMMAFIT对HPGe探测器测量到的特征伽马峰进行拟合,获得全能峰的净面积。分析全能峰净面积与样品质量之间的响应,对探测器的探测效率变化造成的非线性响应进行修正,得到不同元素的校准曲线,结果显示各元素修正后的校准曲线均具有良好的线型关系。对不同元素的质量检测限进行分析,不同金属元素的质量检测限分别为Fe（44 g）,Ti（25 g）,Cr（33 g）,Ni（108 g）和Cu（72 g）。利用测量系统对不锈钢合金样品中的Fe和Cr元素含量测量开展了研究,通过测量标准样品建立了Fe和Cr元素的定标曲线,并对未知样品进行了测量分析。同时与X射线荧光光谱（XRF）测量结果进行了对比分析,结果表明两种方法的Fe元素和Cr元素测量值偏差分别为4.08%和2.97%。研究结果表明,利用PGNAA技术可以对多种金属元素和合金样品进行测量分析,为后续其他金属样品的检测奠定了研究基础。     

Calculation of prompt fission neutron spectra for 235U(n,f)

The prompt fission neutron spectra for the neutron-induced fission of ²³⁵U at E_n < 5 MeV are calculated using nuclear evaporation theory with a semi-empirical model, in which the nonconstant and constant temperatures related to the Fermi gas model are taken into account. The calculated prompt fission neutron spectra reproduce the experimental data well. For the n(thermal)+²³⁵U reaction, the average nuclear temperature of the fission fragment, and the probability distribution of the nuclear temperature, are discussed and compared with the Los Alamos model. The energy carried away by γ rays emitted from each fragment is also obtained and the results are in good agreement with the existing experimental data.     

Calculation of the reactor neutron time of flight spectrum by convolution technique

It is a very complex and time-consuming process to simulate the nuclear reactor neutron spectrum from the reactor core to the export channel by applying a Monte Carlo program. This paper presents a new method to calculate the neutron spectrum by using the convolution technique which considers the channel transportation as a linear system and the transportation scattering as the response function. It also applies Monte Carlo Neutron and Photon Transport Code （MCNP） to simulate the response function numerically. With the application of convolution technique to calculate the spectrum distribution from the core to the channel, the process is then much more convenient only with the simple numerical integral numeration. This saves computer time and reduces some trouble in re-writing of the MCNP program.     

Determinations of plasma density and decay time in the hollow cathode discharge by microwave transmission

The microwave （MW） transmission method is employed to measure both the plasma density and the plasma decay time in the hollow cathode discharge （HCD） in argon at low pressure. The plasma density in DC-driven or pulsed HCD is on the order of 1012 cm-3, which can block the X-band MW effectively. In the case of pulsed HCD, the MW transmittance shows the same waveform as the pulsed current during the rising edge if the driving frequency is low, but with a longer delay during the falling edge. The MW transmittance reaches a constant low level when the driving frequency is high enough. The plasma decay time in the HCD system is measured to be about 100 μs around a pressure of 120 Pa. The ambipolar diffusion is considered to be the major mechanism in the decay process.     

用多群蒙特卡罗方法计算快中子核临界K_(eff)和通量密度

用多群蒙特卡罗方法对快中子核裂变系统进行了临界计算。有效增殖因子κｅｆｆ的计算值与实验结果符合。计算所得中子通量密度的空间分布在球形裂变系统中随半径增大单调下降。中子通量密度的能量分布在由高浓缩铀组成的活性区内里单一能量极大值,其对应能量对于裸球核裂变系统和具有反射层裂变系统分别为０．３５ＭｅＶ和０．２５ＭｅＶ,而在由天然铀组成的反射层中在０．１ＭｅＶ附近出现能量双峰。由通量密度所得中子能谱在无反射层球形裂变系统中随半径增加变硬,在有反射层球形裂变系统中随半径增加变软。     

Direct neutron decay of analogue resonances in ^105Rh

A new method, while takes into account the contribution of direct neutron decay of analogue resonances to the isomeric ratio resulting from （p,n） reaction, is used to analyse the published experimental data for the reaction ^104Ru（p,n） ^104Rh and also estimate a minimum probability of direct decay.     

VITESS polarized neutron suite: allows for the simulation of performance of any existing polarized neutron scattering instrument

As neutron simulations packages are used for analysis of the expected performance for practically all newly built neutron instruments, possibilities for simulations with polarized neutrons have been relatively underdeveloped.During the last years we developed a new approach for the representation of time-dependent magnetic fields (both in magnitude and direction) for the VITESS simulation package. This allowed us to simulate the neutron spin dynamics in practically all polarized neutron devices (RF neutron flipper, adiabatic gradient RF flipper, the Drabkin resonator, etc.). In this article the above-mentioned VITESS instrument components (modules) will be presented and the simulated performance of a number of polarized neutron scattering instruments (NRSE, MIEZE, SESANS, etc.) will be demonstrated.Thus, we practically complete the polarized neutron suite of the VITESS, which seems sufficient for the simulation of performance of any existing polarized neutron scattering instrument. Future work will be concentrated on developments of dedicated sample modules (kernels) to allow for virtual experiments with VITESS.     

Study of neutron response for two hybrid RPC setups using the GEANT4 MC simulation approach

The present article describes a detailed neutron simulation study in the energy range 10~(-10) MeV to 1.0 GeV for two different RPC configurations.The simulation studies were taken by using the GEANT4 MC code.Aluminum was utilized on the GND and readout strips for the (a) Bakelite-based and (b) glass-based RPCs.For the former type of RPC setup the neutron sensitivity for the isotropic source was S_n=2.702×10~(-2) at E_n=1.0 GeV, while for the latter type of RPC, the neutron sensitivity for the same source was evaluated as S_n=4.049×10~(-2) at E_n=1.0 geV.These results were further compared with the previous RPC configuration in which copper was used for ground and pickup pads.Additionally A1 was employed at (GND+strips) of the phosphate glass RPC setup and compared with the copper-based phosphate glass RPC.Good agreement with sensitivity values was obtained with the current and previous simulation results.     

多群输运-燃耗耦合蒙特卡罗计算

介绍了三维多群中子输运-燃耗耦合P3近似蒙特卡罗程序MCMG-BURN,该程序是在连续截面蒙特卡罗程序MCNP和反应堆栅元均匀化程序WIMS基础上发展而来的,使用多群截面为模拟临界实验堆和高通量工程实验堆,取得与MCNP和实验一致的结果,MCMG-BURN具有与MCNP相同的精度,但计算时间较MCNP要少得多。