MCNP程序计算中国人特性头模BNCT剂量分布

对国际上普遍采用的Synder人体头部模型进行修正，建立了有中国人解剖模型特征的几何模型和用于BNCT的人体头部MCNP计算模型，建立了一套用于BNCT治疗计划的软件。在软件模型的基础上分别计算了不同能量的中子进行治疗时的肿瘤及正常组织剂量分布，并对计算结果进行了分析。     

基于Synder修正模型的硼中子俘获治疗剂量深度分布计算

目前，对硼中子俘获治疗（BNCT）进行剂量计算时普遍使用Synder模型，本文依据中国人的头部解剖特征，对该模型进行重建，建立了修正Synder模型。在该模型基础上，利用MCNP程序编制出放射性治疗软件，计算了无含硼药物和有含硼药物时不同能量的中子在头部的剂量深度分布，并对计算结果进行比较分析。计算结果为我国即将进行的BNCT临床治疗研究有一定的助益。     

基于重复结构卡的BNCT人体头部精细模型剂量分布计算

针对目前BNCT治疗脑胶质瘤所采用的头部模型的粗略性,用MCNP程序的Universe和Fill重复结构卡对人体头部的精细模型进行描述,分别使用热中子、超热中子和快中子对大脑在有、无载硼剂时的剂量分布进行了计算,得到了剂量率随深度分布的曲线.计算结果与有关文献的报道结果相吻合,本文所构建的人体头部精细模型是正确的.     

MCNP计算含肿瘤Snyder修正头部模型的硼中子俘获治疗剂量

为得出硼中子俘获治疗(BNCT)中不同能量中子在含肿瘤Snyder修正头部模型内的深度-剂量曲线,籍以进一步理解BNCT原理,优化BNCT治疗中子源的能谱分布,本文利用MCNP模拟计算0.025 3 eV、1 eV、1 keV、10 keV、100 keV、1 MeV和混合能量的超热中子源在含肿瘤Snyder修正头部模型内的硼剂量、热中子剂量、超热和快中子剂量以及次级光子剂量组分的深度-剂量分布,并在此基础上得到总的相对生物学剂量的深度-剂量分布,以判断不同能量组中子源在BNCT中的优劣。结果表明,热中子头皮浅表处硼剂量高于肿瘤区硼剂量;快中子源硼剂量小,但其剂量组分中超热和快中子剂量过大;超热中子具有一定的穿透性,在脑深部肿瘤区形成了较高的硼剂量和总的相对生物学剂量。说明超热中子具有良好的BNCT治疗效果,热中子和快中子不适宜用于脑部BNCT治疗。     

高压交流输电线工频电磁场对人体头部的影响

高压交流输电线是产生工频电磁暴露环境问题的重要因素之一.为了研究高压交流输电线下人体头部周围电磁场的安全性,本研究以220 kV交流输电线为主要研究对象,利用COMSOL Multiphysics有限元软件建立交流输电线下的三维人体头部工频电磁场有限元仿真模型,计算不同距离下人体头部的电磁场分布情况并判断其安全性.结果...     

MCNP程序几何描述能力扩展及应用测试

为使MCNP程序能模拟数百万规模的反应堆“pin-by-pin”问题和医学体素模型，本文对MCNP程序进行了改进，使几何块、几何面数量可扩展。改进后的程序对硼中子俘获治疗（BNCT）的人体大脑进行几何建模，栅元数量达百万量级；计算了大脑的中子、光子吸收剂量率随深度的变化，为大脑BNCT提供理论支持。此外，对百万规模的“Like n But”重复结构模型进行了串、并行测试，验证了几何规模扩展后程序计算的正确性。     

硼中子俘获治疗人头开颅模型内宏观吸收剂量分布

应用MCNP 4B程序模拟计算了硼中子俘获治疗(BNCT)人体头颅等效模型开颅时的宏观吸收剂量分布.采用含有肿瘤体的双椭球结构的等效模型,模拟了深部肿瘤、浅部肿瘤和表层肿瘤3个算例,计算了正常组织及肿瘤体内的宏观吸收剂量分布.计算结果表明,照射后部分网格的吸收剂量低于治疗标准18 Gy,但在同一网格中,肿瘤越靠近表层,吸收剂量越大,治疗效果越好.     

基于加速器的硼中子俘获治疗装置束流整形体的设计及其临床参数研究

在硼中子俘获治疗(BNCT)中,束流整形体是BNCT装置产生高品质中子束的关键部件之一,其设计至关重要。本文基于2.5 MeV质子打锂靶产生中子的过程,对加速器驱动的BNCT中子源的束流整形体进行了可行性方案设计,研究了慢化体厚度差异对出口束流品质、头部模型中的剂量分布和临床参数等方面的影响。研究表明,可行性方案设计在30 mA质子束流驱动下,可达到IAEA对束流品质的要求;在本文3种慢化体厚度设计下,随着慢化体厚度的增加,出口超热中子束流强度减小,快中子份额减小,进一步导致优势深度变浅,正常组织最大剂量率减小,治疗时间变长。     

基于加速器的硼中子俘获治疗装置束流整形体的设计及其临床参数研究

在硼中子俘获治疗（BNCT）中,束流整形体是BNCT装置产生高品质中子束的关键部件之一,其设计至关重要。本文基于25 MeV质子打锂靶产生中子的过程,对加速器驱动的BNCT中子源的束流整形体进行了可行性方案设计,研究了慢化体厚度差异对出口束流品质、头部模型中的剂量分布和临床参数等方面的影响。研究表明,可行性方案设计在30 mA质子束流驱动下,可达到IAEA对束流品质的要求;在本文3种慢化体厚度设计下,随着慢化体厚度的增加,出口超热中子束流强度减小,快中子份额减小,进一步导致优势深度变浅,正常组织最大剂量率减小,治疗时间变长。     

用于硼中子俘获治疗的强流质子回旋加速器中心区结构优化设计

中国原子能科学研究院目前正在研制用于硼中子俘获治疗（BNCT）的强流质子回旋加速器,该加速器设计引出能量14 MeV、质子束流强大于1 mA。相比引出流强为400 μA的PET回旋加速器,BNCT强流质子回旋加速器对中心区相位接收度和轴向聚焦的要求更高。为实现mA量级的束流的加速和引出,BNCT强流质子回旋加速器采取了增加负氢束流注入能量、增大磁铁镶条孔径、使用用于增大Dee盒头部张角的阶梯状结构及调整加速间隙的入口和出口高度等一系列中心区结构优化设计,有效地提高了中心区的相位接收度,改善了轴向电聚焦。在新的离子源注入能量下通过数值计算得到实测场下的轴向电聚焦和间隙高度的关系,选取合适的间隙高度获得最佳的轴向聚焦,从而确定了mA量级束流的注入和加速的中心区结构。同时在设计中考虑空间电荷效应的影响,计算了不同流强下的束流尺寸变化。中心区结构在实测磁场下的优化设计计算结果表明,BNCT强流质子回旋加速器中心区的束流对中好于0.5 mm,相位接收度大于40°,中心区最高可接收流强3 mA。目前,新的中心区结构已进入机械加工阶段。     

BNCT人头体模内剂量分布计算

用修正的Synder人头体模几何模型和ICRU-46中的材料数据，用MCNP-4B程序对0．0253ev、1kev、2keV、10keV、100keV、1MeV单能中子束，0．2、0．5、1、2、5、10MeV单能光子束，以及与当前硼中子俘获治疗(BNCT)临床中使用的超热中子相似的超热中子束，计算了在人头体模中的剂量分布，计算结果与有关文献报道的结果一致，初步校验了我们正在编制的BNCT治疗计划软件。     

Evolutionary design of reactor vessel assembly for liquid metal cooled battery

The Battery Omnibus Reactor Integral System (BORIS) is being developed as a multipurpose integral fast reactor at the Seoul National University. This paper focuses on developing design methodology for optimizing geometry of the liquid metal cooled reactor vessel assembly. The key design parameters and constraints are chosen considering technical specifications such as thermal limits and manufacturing difficulties. The evolution strategy is adopted in optimizing the geometry. Two objective functions are selected based upon economic and thermohydraulic reasons. Optimization is carried out in the following steps. First, selected design values are supplied to the momentum integral model code to evaluate steady-state mass flow rate and coolant temperature distribution of the reactor vessel assembly utilizing the thermodynamic boundary condition on heat exchanger calculated by the thermodynamics code. Second, the objective function values are calculated and compared against the previous results. The steps are repeated until an optimum value is obtained. Results of the improved design of the reactor vessel assembly are presented and their characteristics are discussed.     

Investigating the advantages and disadvantages of realistic approach and porous approach for closely packed pebbles in CFD simulation

A pebble bed geometry is usually adopted for high-temperature gas-cooled reactors (HTGRs), which exhibits inherently safe performance, high conversion efficiency, and low power density design. It is important to understand the thermal-hydraulic characteristics of HTGR core for optimum design and safe operation. Therefore, this study investigates the thermal-hydraulic behaviors in a segment of pebbles predicted by the Reynolds-averaged Navier-Stokes (RANS) computational fluid dynamics (CFD) model using porous and realistic approaches for the complicated geometry. The advantages of each approach's methodology for the closely packed pebble geometry can be revealed by comparing the calculated results. In an engineering application, a CFD simulation with the porous approach for the pebble geometry can quickly and reasonably capture the averaged behaviors of the thermal-hydraulic parameters as the gas flows through the core, including the pressure drop and temperature increase. However, it is necessary to utilize the realistic approach for this complicated geometry to obtain the detailed and localized characteristics within the fluid and solid fuel regions. The present simulation results can provide useful information to help CFD researchers to determine an appropriate approach to be used when investigating the thermal-hydraulic characteristics within the reactor core of a closely packed pebble bed.     

球床内流动与传热特性等效模型的优化研究

提出研究球形燃料元件水冷堆热工-水力问题的等效模型方法。运用计算流体力学软件对窄间隙带环肋片细棒束结构进行三维建模、网格划分和流动传热模拟计算,得到表观流速在0.076~0.334 m/s范围内的压降和换热系数,并与已有的球床实验数据进行比较。根据比较结果对等效模型几何参数进行优化,得到最优等效模型。研究结果表明:最优等效模型与球床的流动与传热特性一致,从数值方法上证明采用等效模型方法对球形燃料元件水冷堆热工-水力问题进行研究是可行的。     

穿透概率法求解二维六角形轻水堆燃料组件中子通量密度分布

研究利用穿透概率法求解二维六角形轻水堆燃料组件内中子通量密度分布。子区内中子源采用线性分布,子区表面通量密度在方向上采用简化6P1近似。提出了六角形组件周边水隙的处理方法。根据提出的模型,编制了TPHEX－C程序,并对六角形组件进行了计算,结果与蒙特卡罗方法计算的结果符合良好。     

Nuclear heating and helium production at the inboard divertor rail for DEMO

Monte Carlo simulations were carried out for the DEMO model. Distributions of both the nuclear heating and the helium production in the area between the blanket and the divertor were calculated with the MCNP5 code for the reference case, when the DEMO geometry was not changed. Next a segment of the divertor and the lower part of the manifold were modified. Two new arrangements were studied. The simulations show that for one of the examined cases the helium production and the nuclear heating can be reduced roughly three or even four times in the investigated area. Besides the nuclear heating and the He production were estimated at the fastener (bolt head). The use of the modified divertor and a rail protecting the blanket is essential in the DEMO design.     

针对球床的三维特征线方法几何建模研究

特征线方法通过在计算区域密置特征线来计算角通量,对于计算区域的材料分布和几何结构没有要求,因此特征线方法的几何处理能力受制于几何描述模块对于各种几何区域的描述能力。基于体素构造（CSG）方法,开发了三维特征线程序MOCP的几何描述模块。该几何描述模块可描述随机分布的球床。针对球形燃料的网格划分方式进行了研究,临界球的计算结果表明,当径向网格超过30层时,k_eff的相对误差小于0.1%。通过对几何描述方式的改进大幅提高了三维特征线追踪的效率,并且实现了在各种形状边界上的特征线布置。     

A way forward for the development of an exposure computational model to computed tomography dosimetry

A way forward for the development of an exposure computational model to computed tomography dosimetry has been presented. In this way, an exposure computational model (ECM) for computed tomography (CT) dosimetry has been developed and validated through comparison with experimental results. For the development of the ECM, X-ray spectra generator codes have been evaluated and the head bow tie filter has been modelled through a mathematical equation. EGS4 and EGSnrc have been used for simulating the radiation transport by the ECM. Geometrical phantoms, commonly used in CT dosimetry, have been modelled by IDN software. MAX06 has also been used to simulate an adult male patient submitted for CT examinations. The evaluation of the X-ray spectra generator codes in CT dosimetry showed dependence with tube filtration (or HVL value). More generally, with the increment of total filtration (or HVL value) the X-raytbc becomes the best X-ray spectra generator code for CT dosimetry. The EGSnrc/X-raytbc combination has calculated C_100,c in better concordance with C_100,c measured in two different CT scanners. For a Toshiba CT scanner, the average percentage difference between the calculated C_100,c values and measured C_100,c values was 8.2%. Whilst for a GE CT scanner, the average percentage difference was 10.4%. By the measurements of air kerma through a prototype head bow tie filter a third-order exponential decay equation was found. C_100,c and C_100,p values calculated by the ECM are in good agreement with values measured at a specific CT scanner. A maximum percentage difference of 2% has been found in the PMMA CT head phantoms, demonstrating effective modelling of the head bow tie filter by the equation. The absorbed and effective doses calculated by the ECM developed in this work have been compared to those calculated by the ECM of Jones and Shrimpton for an adult male patient. For a head examination the absorbed dose values calculated by the ECM developed by Jones and Shrimpton overestimates up to three times the absorbed dose to brain compared to the ECM developed in this work. The effective dose calculated by the ECM of Jones and Shrimpton was 26% greater than effective dose calculated by the ECM developed in this work.