JMCT光子-电子耦合输运模拟计算研究

为满足光子-电子耦合输运应用模拟需求,自主研发了JMCT光子-电子耦合输运功能,并实现了多种光电耦合输运处理方式,以便满足不同的工程需求。利用光子-电子耦合输运典型算例验证了JMCT光子-电子耦合输运功能的正确性,并应用到了探测器响应函数模拟、闪光照相模拟计算中,表明JMCT在实验核物理、核分析技术应用等方面发挥着越来越重要的作用。     

C/O比能谱测井中碘化钠探测器对g射线响应函数的计算

 给出了中子g 能谱测井中NaI闪烁探测器对g 射线响应函数的计算方法,计算了3×3NAI（T1）探测晶体对能量直到25MeV的g 射线的能量沉积谱和响应函数。计算结果与实验结果符合较好。     

BEAVRS基准模型热零功率状态的JMCT分析

使用JMCT (J Monte Carlo Transport Code)对来自MIT的全堆芯pin-by-pin精细建模的国际基准模型BEAVRS的热零功率(HZP)状态进行了模拟计算, 并与测试数据进行了对比和分析. 比较的物理量包括临界本征值、控制棒价值、反应性温度系数、轴向积分的全堆探测器测量值和不同位置四个组件轴向相对功率密度分布. HZP状态下不同控制棒位置插入和硼浓度的临界本征值计算, JMCT结果与理论值1.000 的误差小于0.2%, 控制棒价值计算结果与测量值符合. JMCT对轴向积分的探测器径向相对功率分布和四个组件的轴向归一化的探测器的计算结果与测量值进行了比较和分析, 计算结果与测量值一致, 同时清晰地展示了模型增加格架后, 轴向功率曲线在相应位置出现下凹的现象. 此外, JMCT给出了轴向积分的组件径向相对功率密度分布和轴向相对功率最大处(Z轴位置)的pin径向相对功率密度分布, 并与国际知名程序MC21结果进行了对比, 两个图像都符合得非常好. 随着计算机与并行计算的高速发展, 蒙特卡罗程序开始从传统的反应堆校验工具向反应堆设计工具转变.     

JMCT软件的自动源偏倚抽样功能及其应用

介绍JMCT（J Monte Carlo Transport）软件的多群中子伴随输运功能以及基于伴随通量的自动源偏倚抽样功能.对某商用压水堆屏蔽模型的模拟计算表明,采用自动源偏倚后,JMCT的模拟结果与实验值符合较好,比MCNP程序采用几何重要性方法的计算效率大幅提高.     

BC537探测器中γ射线的响应函数测量与蒙特卡罗模拟

为了将氘化液闪探测器(BC537)测量的反冲电子谱转换为γ射线能谱,利用标准γ点源对BC537探测器的响应进行了测量并运用基于蒙特卡罗方法的Geant4程序计算了BC537探测器探测γ射线的响应函数。讨论了探测器建模中有无铝壳和入射γ射线束流半径对探测效率和响应函数的影响。对比模拟和实验测量的反冲电子谱,两者符合较好。利用模拟的响应函数和实验测量标准γ源Cs-137和Co-60以及AmBe源在BC537探测器中的反冲电子谱,经迭代法解谱得到了对应的标准γ射线能谱,验证了模拟参数的合理性以及该响应函数的实用性。     

蒙特卡罗粒子输运程序JMCT研制

介绍了具有自主知识产权的蒙特卡罗(MC)粒子输运程序JMCT的初步研制成果。JMCT基于三维组合几何支撑软件框架JCOGIN,采用模块化,分成多层管理结构,可处理多群碰撞和连续能量碰撞,可进行粒子并行和区域分解并行两种并行方法,并具有良好的可扩展性和高速通信技术,同时配有可视化建模前处理软件。介绍了JMCT采用的多群物质碰撞机制,展示了程序模拟计算测试模型的结果,与MCNP程序计算结果一致。JMCT串行计算速度相比MCNP提高了约3 倍;在20 480个处理器核上模拟2109样本,并行效率可达70%。     

堆外探测器响应函数三维空间分布计算

堆外探测器响应函数代表了堆芯活性区各组件对堆外探测器计数率的贡献,反映了堆芯功率分布与探测器计数率的关系。研究了三维离散纵标法(SN)程序TORT的共轭输运方法,并开发相应的处理程序,实现了柱坐标下的三维共轭中子注量率到压水堆各燃料组件响应函数的转换。并基于CAP1400核电厂反应堆模型,分析了其堆外探测器响应函数空间分布的特性,与采用TORT多次正向输运计算结果进行了对比分析,两者符合较好。通过本文研究,实现了压水堆核电厂堆外探测器响应函数的三维空间分布计算。     

圆柱腔体光电输运的蒙特卡罗模拟

应用三维并行蒙特卡罗程序JMCT, 计算了特征温度分别为1, 3, 5, 8keV的黑体谱X射线入射到铝、二氧化硅、金的表面的背散射光电产额和电子能谱, 并与文献结果进行对比, 验证了程序的正确性, 进而针对系统电磁脉冲(SGEMP)研究中的典型几何结构——金属圆柱腔体, 模拟计算了其在黑体谱X射线照射下的光电输运过程, 用温度为1keV、注量为1J/m2的黑体谱X射线平行照射圆柱腔侧面, 半个侧面发射光电子, 计算得出了和方位角相关的不同面上发射光电子的光电产额、能谱分布和角分布, 结果表明掠入射的X射线会产生更高的光电产额; 光电子的发射角分布都基本符合余弦角分布的规律。     

JMCT在CPR1000工程设计中的验证与确认

CPR1000系列反应堆是目前国内广泛应用的第二代压水堆型号之一，蒙特卡罗程序在CPR1000系列反应堆的验证与确认是该程序实现反应堆工程设计应用的关键环节。基于某CPR1000机组实际参数，使用由国内单位研发的蒙特卡罗程序JMCT在该机组开展了粒子输运建模计算，分别进行了临界计算和固定源计算，并进行了验证与确认。对于临界计算，采用JMCT建立了全堆芯pin-by-pin模型，计算了堆芯有效增殖因子和功率分布。对于固定源计算，建立适用于屏蔽分析的反应堆模型和辐照监督管精细结构模型，计算了两个核电机组多个循环的辐照监督管探测器位置累积快中子注量。通过将JMCT的计算结果与参考程序的计算结果、反应堆实际测量值进行了对比，验证了JMCT程序在CPR1000反应堆工程设计中的实际使用效果，证明了JMCT程序具备工程级的计算精度。     

特征γ射线谱分析的蒙特卡罗模拟技术

蒙特卡罗方法(MC)是模拟核探测问题的理想方法,用中子照射客体,中子诱发产生非弹γ和俘获γ,通过特征γ射线能谱和时间谱分析,确定客体核素组成和重量百分比.本文基于非弹γ和俘获γ时间门测量技术,给出了脉冲源发射下探测器响应计数公式.在中子与核作用产生次级光子方面,采用期望值估计(expect value estimator,EVE)产光.为了避免大量小权光子模拟带来的计算存储量增加,设计了EVE产光与直接估计(direct estimator,DE)产光耦合.仅增加少量计算时间,便实现了特征γ射线解谱.数值模拟在自主MC软件JMCT上开展,计算结果初步验证了方法的正确有效性.     

蒙特卡罗输运模拟软件JMCT的深穿透屏蔽计算

核设施辐射屏蔽计算,由于其大规模计算及深穿透等特性,一直是蒙特卡罗方法工程应用的难点之一。采用我国自主研发的三维中子-光子蒙特卡罗粒子输运模拟软件JMCT,结合可视化建模工具JLAMT,对OECD国际基准例题Winfrith Iron/Water Benchmark Experiment(ASPIS)两例实验装置进行建模与计算分析, 并将计算结果与实验值及MCNP计算值进行对比。结果表明,JMCT计算值与MCNP计算值符合较好,其中Winfrith Iron Benchmark Experiment(ASPIS)最大偏差不超过7%,平均偏差1.3%;Winfrith Water Benchmark Experiment(ASPIS)最大偏差小于20%,平均偏差小于10%,证明了JMCT在屏蔽计算以及深穿透问题的可靠性与工程应用性。     

基于VENUS-III国际基准模型的JMCT程序验证

基于自主研制的三维中子-光子耦合输运蒙特卡罗通用程序JMCT（J Monte Carlo Transport Code）,采用连续点截面,对国际基准屏蔽VENUS-III模型开展精细建模和中子输运临界及屏蔽计算.临界计算得到系统k_eff、重要区域的通量及能谱.结果表明,JMCT和MCNP程序的重要区域体通量计数吻合较好,偏差均在1%以内.深穿透屏蔽计算采用外源模式,点探测器计数,JMCT计算值与实验测量值偏差在15%以内,满足屏蔽设计对误差的要求.初步验证了JMCT程序临界及屏蔽计算的可用性.     

PET image reconstruction with a system matrix containing point spread function derived from single photon incidence response

A point spread function(PSF)for the blurring component in positron emission tomography(PET)is studied.The PSF matrix is derived from the single photon incidence response function.A statistical iterative reconstruction(IR)method based on the system matrix containing the PSF is developed.More specifically,the gamma photon incidence upon a crystal array is simulated by Monte Carlo(MC)simulation,and then the single photon incidence response functions are calculated.Subsequently,the single photon incidence response functions are used to compute the coincidence blurring factor according to the physical process of PET coincidence detection.Through weighting the ordinary system matrix response by the coincidence blurring factors,the IR system matrix containing the PSF is finally established.By using this system matrix,the image is reconstructed by an ordered subset expectation maximization(OSEM)algorithm.The experimental results show that the proposed system matrix can substantially improve the image radial resolution,contrast,and noise property.Furthermore,the simulated single gamma-ray incidence response function depends only on the crystal configuration,so the method could be extended to any PET scanner with the same detector crystal configuration.     

JMCT的高浓铀模型验证计算北大核心CSCD

为了对JMCT程序的准确性和适用性进行验证,从国际临界基准库中选取了56个模型,通过使用JLAMT程序进行建模,然后利用JMCT程序计算了模型的有效增殖因子,并与基准值、MCNP程序计算结果进行对比。计算结果表明,JMCT计算值基本都在基准值的3倍标准差以内,且JMCT计算结果和基准值的相对偏差基本都在2%以下。在一定程度上验证了JMCT程序的准确性和适用性,为后续JMCT程序的使用验证提供借鉴。     

JMCT程序临界安全基准校验计算与分析

JMCT程序是北京计算数学与应用物理研究所自主开发的蒙特卡罗方法粒子输运计算程序。从国际临界安全实验数据库中选取棒栅类、U系、Pu系、233U系实验方案对JMCT程序进行验证,验证涵盖了常见裂变元素（如U,Pu等）从低富集度到高富集度的快、热能区,同时也包含了常见的中子毒物以及反射层材料。将JMCT程序的计算结果与基准实验值进行对比,并且与MCNP,MONK程序的计算结果进行了比较。结果表明,在检验的范围内,JMCT程序具有与国际通用蒙特卡罗方法粒子输运程序一样良好的计算精度。     

基于JLAMT可视化建模的JMCT模拟计算

JMCT是中国工程物理研究院高性能数值模拟软件中心粒子输运团队自主研发的三维蒙特卡罗模拟软件,JLAMT为其前处理可视化建模工具。使用JLAMT和JMCT程序对BW,KRITZ,BEAVRS等系列基准题进行了模拟,并对有效增殖系数及计数功能进行了对比分析。其中有效增殖系数计算结果与MCNP5的最大偏差为KRITZ2装载方案19基准题的89.1 pcm,除BEAVRS基准题外的计数结果与MCNP5的偏差基本小于2%,平均偏差在1%左右;BEAVRS基准题功率分布模拟结果与MCNP5及实测值最大偏差分别为7.06%,16.6%,控制棒价值计算与MCNP5及实测值均吻合较好。,     

An intercomparison of Monte Carlo codes used for in-situ gamma-ray spectrometry

In-situ gamma-ray spectrometry is widely used for monitoring of natural as well as man-made radionuclides and corresponding gamma fields in the environment or working places. It finds effective application in the operational and accidental monitoring of nuclear facilities and their vicinity, waste depositories, radioactive contamination measurements and environmental mapping or geological prospecting. In order to determine accurate radionuclide concentrations in these research fields, Monte Carlo codes have recently been used to obtain the efficiency calibration of in-situ gamma-ray detectors.This work presents an inter-comparison between two Monte Carlo codes applied to in-situ gamma-ray spectrometry. On the commercial market, Canberra has its LABSOCS/ISOCS software which is relatively inexpensive. The ISOCS mathematical efficiency calibration software uses a combination of Monte Carlo calculations and discrete ordinate attenuation computations. Efficiencies can be generated in a few minutes in the field and can be modified easily if needed. However, it has been reported in the literature that ISOCS computation method is accurate on average only within 5%, and additionally in order to use LABSOCS/ISOCS it is necessary a previous characterization of the detector by Canberra, which is an expensive process. On the other hand, the multipurpose and open source GEANT4 takes significant computer time and presents a non-friendly but powerful toolkit, independent of the manufacturer of the detector.Different experimental measurements of calibrated sources were performed with a Canberra portable HPGe detector and compared to the results obtained using both Monte Carlo codes. Furthermore, a variety of efficiency calibrations for different radioactive source distributions were calculated and tested, like plane shapes or containers filled with different materials such as soil, water, etc. LabSOCS simulated efficiencies for medium and high energies were given within an accuracy of below 5% for point sources and 10% maximum accuracy for more complicated geometries. Accuracy for LabSOCS decreased for low energy emissions. Finally an analysis and discussion of the results and the main differences found between LabSOCS and GEANT4 were performed.     

Comparison of two position sensitive gamma-ray detectors based on continuous YAP and pixellated NaI(TI) for nuclear medical imaging applications

Dedicated position sensitive gamma-ray detectors based on position sensitive photomultiplier tubes (PSPMTs) coupled to scintillation crystals, have been used for the construction of compact gamma-ray imaging systems, suitable for nuclear medical imaging applications such as small animal imaging and single organ imaging and scintimammography. In this work, the performance of two gamma-ray detectors: a continuous YAP scintillation crystal coupled to a Hamamastu R2486 PSPMT and a pixellated NaI(TI) scintillation array crystal coupled to the same PSPMT, is compared. The results show that the gamma-ray detector based on a pixellated NaI(TI) scintillation array crystal is a promising candidate for nuclear medical imaging applications,since their performance in terms of position linearity, spatial resolution and effective field of view (FOV) is superior than that of the gamma-ray detector based on a continuous YAP scintillation crystal. However, a better photodetector (Hamamatau H8500 Flat Panel PMT, for example) coupled to the continuous crystal is also likely a good selection for nuclear medicine imaging applications.