MC法对移动式工业γ探伤机周边辐射模拟

为准确划定工业γ探伤机的控制区与监督区,应用MCNP5程序构建了移动式γ射线机计算模型。该模型充分考虑了工业γ探伤机散射对周围剂量的贡献,可有效地应用于工业γ探伤机控制区与监督区的划定与环境影响评价。实验结果表明:MCNP程序计算结果与经验公式结果基本一致,MC模拟方法对移动式工业γ射线机周边辐射剂量估算是可行的。     

蒙特卡罗均匀化与多群蒙特卡罗输运研究

基于蒙特卡罗方法(MCNP)进行组件均匀化产生少群常数继而进行堆芯计算,是MCNP应用于堆芯物理分析的一种可行方案。研究MCNP统计产生少群截面以及等效均匀化理论应用于多群蒙特卡罗计算的方法,并进行数值验证。结果表明,本文提出的利用MCNP模拟产生等效均匀化少群常数的方法是可行的,在保证预定精度的条件下提高了效率。     

极大似然法反演γ特征峰位的能力研究

极大似然法反演γ能谱可有效提高γ能谱能量分辨率,为观察该方法反演γ特征峰位的能力,使用蒙特卡罗模拟程序MCNP (Monte Carlo N Particle Transport Code)计算了一台10.16 cm×10.16 cm×40.64 cm NaI(Tl)探测器的能量响应矩阵,采用极大似然法和该能量响应矩阵对包含10种不同能量特征峰的MCNP模拟能谱、铅屏蔽室和实验室自然环境中测得的152Eu点源的γ能谱进行反演。结果显示:对模拟的γ能谱,反演后特征峰中心道址相对参考值最大偏差为1道;对铅屏蔽室中的152Euγ能谱,反演后特征峰中心道址与实测值偏差小于2道;对实验室自然环境中152Euγ能谱,反演后特征峰中心道址与实测值偏差小于4道。     

基于CADIS方法的蒙特卡罗深穿透屏蔽计算方差降低方法研究

正深穿透问题是指由于屏蔽层过厚、源强较弱或探测器体积较小导致粒子输运计算结果偏低的问题。针对于蒙特卡罗屏蔽计算中的深穿透问题,利用一致共轭驱动重要性抽样(CADIS)方法的相应理论,实现了蒙特卡罗软件MCNP减小计算方差,可通过蒙特卡罗方法的共轭计算来得到共轭通量,经过CADIS方法推导出的公式计算得到权窗参数和源偏倚参数。     

不同海拔高度下γ射线空气衰减系数的计算

在航空γ剂量率测量过程中由于海拔高度跨度大,γ射线空气衰减系数会受到海拔高度、温度、气压与空气密度的影响,故需要进行相应修正。利用蒙特卡罗（MCNP）法模拟γ射线在不同空气密度下的线衰减系数。利用经验公式计算不同海拔高度下的空气密度,利用MCNP法建立γ谱仪模型,计算不同海拔高度、不同密度条件下的γ光子注量,根据指数衰减原理计算不同空气密度下的线衰减系数。结果表明,由经验公式求出的空气密度模拟得出的空气质量衰减系数与美国NIST推荐值最大相对误差为-17.3%;在γ射线参考辐射场中用衰减板进行实验验证,⁶⁰Co源的最大相对误差为6.0%,¹³⁷Cs源的最大相对误差为5.3%。本工作为后续低空近地辐射剂量的研究工作奠定了基础。     

体源探测效率计算及修正方法研究

用MCNP程序计算HPGe γ探测器与体源有一定距离时的探测效率,该方法对于体源探测效率的刻度有着重要意义。但是由于模型的不确定因素影响,计算结果可能有一定的偏差,充分考虑了影响偏差的因素,采用比较校正法推导了HPGeγ探测器计算体源探测效率修正数学公式。通过实验比较和理论比较方法验证修正公式,比较结果表明：MCNP程序计算体源探测效率可以作为体源探测效率刻度的有效手段。     

航空放射性测量的模拟计算

航测系统刻度主要有实验刻度法、模拟实验刻度法、Beck法和蒙特卡洛法.将模拟实验刻度法与蒙特卡洛方法结合,通过MCNP4c程序对系统进行模拟,计算不同高度下对点源的计数,并与木板模拟实验结果对比,得到航测系统在不同高度下计数率的变化规律,并计算出转换因子公式,对今后航空放射性测量高度校正的研究具有指导意义.     

舱室内γ外照射剂量快速估算方法的比较

舱室内γ外照射剂量的快速估算对于核动力船舶核事故后果评价、核应急决策等具有重要意义,但是目前对于舱室内γ外照射剂量的快速估算尚无明确的标准或统一公式。采用MCNP程序计算结果作为基准,对烟羽浸没公式和点核积分公式这2种快速估算方法进行了评估,详细分析了这2种估算方法在不同形状、不同体积舱室情况下的估算结果误差及原因。结果表明,舱室的形状越偏离半球体形状、体积越大,公式估算结果与MCNP程序计算结果偏差越大:有限烟羽浸没公式的误差约为30%,点核积分公式的误差约为10%。因此,在实际工程应用时,点核积分公式可提供更为准确和快速的估算结果。      

堆用蒙特卡罗程序RMC的全堆计算研究

使用清华大学的"探索100"高性能并行计算机,基于美国核能署数据中心的连续能量全堆基准计算模型和法国电力集团的多群全堆基准计算模型,就通用蒙特卡罗程序(MCNP)全堆大规模并行计算开展了研究。针对堆用蒙特卡罗程序(RMC)与MCNP的全堆计算性能进行系统的比较研究。结果表明,MCNP在并行模式和计数器性能等方面均有不足,这些不足严重影响MCNP在反应堆全堆计算上的效率。而RMC在这些问题上取得了较大的改善,能够适用于反应堆全堆精细功率密度计算。因而,在反应堆全堆计算性能上,RMC优于MCNP。     

复合型种子源~(125)I-~(103)Pd剂量场分布的蒙特卡罗模拟与实验测定

在相同参数条件下,使用MCNP5、EGSnrc两种蒙特卡罗方法模拟和实验测定~(125)Ⅰ-~(103)Pd复合种子源剂量场分布情况,实验中采用LiF热释光剂量片(GR-200)记录吸收剂量,有机玻璃为组织等效材料。通过与实验结果比较,两种程序在模拟粒子输运方法、几何描述、材料截面数据等方面结果不同,但是两种程序计算结果与实验符合较好。结果表明,MCNP5和EGSnrc可准确计算种子源剂量场分布。EGSnrc得到的剂量数据更加准确。     

1.5MeV电子辐照平台屏蔽改造

针对一台功率为15kW的1.5 MeV电子辐照平台,进行了屏蔽计算分析与改造设计工作。根据辐照平台厂房布局建立三维模型,使用蒙特卡罗方法进行了相应屏蔽计算。通过对辐照平台主屏蔽体外光子剂量率的计算,对已有建筑物墙体的屏蔽效果进行评估。评估结果表明,建筑物四周墙体厚度满足设计要求。对辐照室和门洞等局部位置进行了屏蔽计算设计,通过对不同屏蔽厚度的计算结果进行比较,给出了满足设计要求的合理可行的设计方案。为验证屏蔽计算结果,在工程验收阶段,对周围人员活动区域进行了现场测量。测量结果表明,辐照平台原有主体屏蔽及新增局部屏蔽可使光子剂量率低于设计目标值,满足防护要求。     

~(60)C0-γ治疗室迷路内照射量率的实测和估算

本文报道~(60)o-γ射线治疗室迷路内射线照射量率的实际测量,探讨了迷路内照射量率的变化规律,初步总结出估算迷路照射量率的计算公式,为迷路的防护监督、辐射事故剂量的估算以及迷路防护墙厚度和迷路外入口防护门的设计提供了参考依据。     

Modeling deformation and failure of fast reactor cladding during simulated accident transients

An analysis is made of burst experiments performed on neutron irradiated cladding tubes. This is done by employing a generalized Voce equation to describe the mechanical deformation of type 316 stainless steel, combined with an empirical creep crack growth law, each modified to account for the effects of irradiation matrix hardening, and irradiation induced grain boundary embrittlement, respectively.The results of this analysis indicate that for large initial hoop stress, failure occurs at relatively low temperature and is controlled by the onset of plastic instability. The increase in failure temperature of irradiated material, in low temperature region, is due to irradiation strengthening. Failure in the case of relatively small initial hoop stress occurs at high temperature where the Voce equation reduces to a power law creep formula. The ductility of irradiated material, in this high tem-temperature region, is adequately described through the use of an empirical intergranular crack growth law used in conjunction with the creep law. The effect of neutron irradiation is to reduce the activation energy for crack propagation from the value for creep to some lower value correlated to independent Dorn rupture parameter measurements. The result is a predicted reduced ductility which translates into a reduction in failure temperature at a given hoop stress value for irradiated material.     

Development of an effective dose calculation method for the downstairs room of a linac facility

ABSTRACT

An effective dose calculation method is important in the design of efficient shields in radiation facilities. Some analytical methods have been shown to provide a simple and quick design analysis; however, no suitable method exists that can be applied to a room located directly under an X-ray irradiation room. We propose a new analytical method that uses the multiple reflection ratio predetermined by a Monte Carlo simulation and the differential dose albedo given by the Chilton–Huddleston semi-empirical equation. Our method is verified by comparison with the Monte Carlo simulation, performed for the case of an electron linac facility with an accelerated energy of 10 MeV, where the shielding floor has a thickness of 1.6–2.0 m and the downstairs room has a height of 0.5–1.5 m. The difference between the effective X-ray doses in the downstairs room calculated via the proposed analytical method and the Monte Carlo simulation is less than 25% when the horizontal distance from the X-ray beam to the evaluation point exceeds 3 m and the evaluation point is set at half of the height of the room. The new analytical method can be efficiently and accurately applied to the calculation of the effective dose.     

用于迷宫屏蔽计算的蒙特卡罗减方差方法研究

本文应用多种减方差技巧提出了强迫指向自动重要抽样（FPAIS）方法,并在MCNP5程序平台实现了该方法。采用该方法对1个多折迷宫算例进行了模拟计算,计算结果与MCNP5程序的直接模拟、DXTRAN球、点通量3种方法的结果进行了比对。基于此算例对FPAIS方法进行了引导面设置和粒子数敏感性分析。结果表明,FPAIS方法在保证一定计算精度的前提下,比其他3种方法的FOM提高2~3个量级,且该方法对引导面设置不敏感、可用性强,对于迷宫屏蔽计算是一种准确、高效的解决方案。     

MCNP模拟钴-60辐照装置空间剂量场

为模拟辐照室中辐照工位外的周围空间剂量场分布,采用蒙特卡罗粒子输运程序MCNP建立钴-60辐照装置模型。以单板源架中心点为坐标原点的笛卡尔坐标系,考虑钴-60源的γ射线非自吸收和自吸收两种情况,研究坐标轴方向上每隔10 cm间距的空气平面的剂量率和坐标轴上剂量率的变化规律。结果表明,辐照室中辐照产品占满辐照工位的情况下,周围空间剂量场空气面剂量率整体较小;单板源架中心坐标轴上的剂量率变化规律更符合二项式拟合函数。在钴-60源γ射线自吸收情况下,单板源架端面坐标轴附近的空气面剂量率明显偏小,且随着空气面远离单板源架,空气面上的高剂量率区域向两侧移动;在钴-60源γ射线非自吸收情况下,单板源架端面处的空气面高剂量区域始终位于坐标轴附近。MCNP理论模拟计算分析对于利用钴-60辐照装置辐照工位外的周围空间剂量场具有重要的实际指导意义。     

A new equation for activity calculation in pulse irradiation:derivation,simulation, and experimental validation

To calculate the radioactivity of product nuclides generated in pulse irradiation, it is generally assumed that the irradiation is approximately continuous in the entire irradiation period(ti) and the flux of the incoming irradiation particle can be obtained by averaging their intensity in each pulse period(T). However, this approximation fails to acknowledge the fact that the product nuclides are not created in each pulse period(T)evenly: They are only produced in a very short pulse width(tp) and then decay in a relatively long rest time(tr = T-tp). Given by the enormous number of pulses, the sum of these decays may not be negligible. To make the activity calculation in accordance with the real situation in pulse irradiation, we scrutinize the details of irradiation and decay processes in each pulse, apply the geometric series to obtain the activity superimposition of millions of pulses,and derive a novel activity equation particularly suitable for pulse irradiation. The experimental results,numerical simulations,and activity measurements from photon activation driven by a pulsed electron LINAC have confirmed the validity of this new equation. The comparison between the new and traditional equations indicates that their discrepancy could be significant under certain conditions. The limitations of the new activity equation for pulse irradiation are discussed as well.     

积分法评估~(60)Co工业辐照装置卡源事故剂量

利用MCNP程序构建简单人体、辐照室、源井、板源模型,对进入辐照室过程中不同位置处工人的吸收剂量率进行了计算,按指数衰减律拟合出吸收剂量率随空间变化的曲线和函数,采用积分法对进入、滞留、撤离辐照室工人的受照剂量进行了计算。结果表明:工人进入、滞留、撤离辐照室总共花费时间为12.7 s,整个过程受照当量剂量为20.61 mSv,与中国辐射防护研究设计院对事故工人个人剂量计检测结果相吻合。该方法可有效地对随空间变化辐射场中的受照工人个人剂量开展评估。     

Empirical Equation of Neutron Diffusion System

An empirical equation between the cross sections and criticality factor was derived by the technique of experimental design and regression analysis. Factorial experiments taking account of interactions between factors was designed with use made of the orthogonal array. Numerical calculation of a two-group, two-core system was performed and an empirical equation derived by regression analysis, resulting in a criticality factor with acceptable accracy.

The technique is general in nature. It should be applicable to learning control and optimum design of reactor systems.     

锆合金辐照蠕变和生长的宏介观模型研究进展

锆合金作为核反应堆堆芯的主要结构材料之一,在服役过程中会发生辐照蠕变和生长行为,严重影响其使用可靠性。预测锆合金的辐照蠕变和生长是保障反应堆安全运行的关键。本文聚焦于两类锆合金构件,包括压水堆用锆合金包壳管及重水堆用Zr-2.5Nb压力管,分别从宏介观尺度详细综述了其辐照变形预测模型。针对适用于包壳管的宏观经验模型及介观力学模型,分别描述了两类模型的特征,重点介绍了介观力学模型的研究现状及最新进展,并对其未来的发展方向提出建议;针对适用于压力管的宏观经验模型,包括加拿大CANDU压力管辐照变形计算方程(简称C6方程)及秦山重水堆压力管辐照变形计算方程(简称秦山方程),分别描述了两类方程的具体形式,并介绍了C6方程国产化的进展。