一种宽能谱多球中子谱仪能量响应的MC模拟

利用蒙特卡罗程序FLUKA模拟计算了聚乙烯慢化球和辅助材料慢化球对低能中子到高能中子的响应函数曲线。结果表明,对纯聚乙烯球来说,随着聚乙烯层厚度的增加,响应曲线峰逐步右移,峰值在高能区有所下降,对20 Me V以上的中子,无论纯聚乙烯球的尺寸有多大,其响应均下降到很低的程度;对辅助材料慢化球来说,中子能量小于1 Me V时,辅助材料慢化球与聚乙烯慢化球的响应曲线相似,但当中子能量大于20 Me V时,中子与辅助材料层发生(n,xn)反应,慢化球的响应呈显著上升趋势。分析计算结果,最终能够确定宽能谱多球中子谱仪的尺寸组合。     

HIRFL人身安全联锁系统的设计与实现

兰州重离子加速器(简称HIRFL),是我国规模最大、加速离子种类最多、能量最高的重离子研究装置,可提供单核子能量达GeV量级的重离子束。HIRFL运行时,束流会在加速器隧道内产生辐射,需要建立一套人身安全联锁系统来保障人员的辐射安全。HIRFL人身安全联锁系统遵循分区联锁、硬件最可靠、失效保护、冗余及独立性、自锁等设计原则,选用了可靠性高的冗余PLC作为核心控制器,并使用了安全性高的联锁部件。本工作的完成保障了HIRFL工作人员的辐射安全,也为同类型加速器装置的人身安全联锁系统设计提供了参考。     

10 MeV同轴腔电子加速器辐射屏蔽设计

中国科学院近代物理研究所自主研制了一台同轴腔电子加速器,能产生10 MeV,10 mA的辐照电子束,建成后有望成为我国首台国产化的花瓣形电子辐照加速器。为保证该装置运行时的辐射安全,为今后同类型装置的辐射屏蔽设计提供参考,对该加速器开展了辐射屏蔽研究。首先结合装置的使用情况给出了一种地上为主机室地下为辐照室的半地下机房结构,然后采用蒙卡程序FLUKA计算了相关墙体的厚度。在蒙卡计算中,基于同轴腔加速器的束流损失特点,建立了适用于该类型装置的蒙卡源项输入模型,充分考虑了决定辐射场的主要束损点,同时设置相对简单。结果表明:在设定的屏蔽外剂量率目标下,以普通混凝土作为屏蔽材料,主机室的侧墙、顶板和辐照室顶板的厚度分别需要160～220,110～150,150 cm。     

类锂离子氯、钙、钪的能级跃迁几率和振子强度的计算

本文描述了利用最弱受约束电子模型理论研究氯(Cl)、钙(Ca)、钪(Sc)元素的类镀离子激发态ns-np,np-nd的能级跃迁几率和振子强度,并把研究结果与文献值做了比较和讨论。     

铜和镍原子的跃迁振子强度F－值的确定

此文阐述了通过实验测定Ｃｕ和Ｎｉ原子的某些激发能级寿命来确定跃迁振子强度Ｆ－值的方法，并给出主要理论公式和确定结果。     

120~430 MeV/u 碳离子的微剂量学特性研究(英文)

单粒子微剂量谱在放射治疗中是一个极其重要的参数,它可以用来评估辐射场的生物学效应。利用蒙特卡洛程序FLUKA模拟计算了由碳离子产生的混合辐射场能量沉积的微观模式。从已公开发表的文献中选取了实验测量300 MeV/u 碳离子的线能能谱,并与相同物理条件下模拟计算得到的线能能谱相比较,结果吻合得很好。此外,还计算了120~430 MeV/u 的碳离子的剂量平均线能能谱、频率平均线能和剂量平均线能。所得到的频率平均线能值为185~ 28.3 keV/m而剂量平均线能值则为272~ 64.1 keV/m。本文的结果对于制定碳离子放射治疗的治疗计划有着重要的意义.Microdosimetric single event spectrum is a significant parameter in radiotherapy, which can be used to evaluate the radiation biological effect. In this paper, microscopic patterns of energy deposition are simulated with Monte Carlo code FLUKA at mixed radiation fields during carbon ions therapy. The results are compared with experimental measured results at 300 MeV/u carbon ion and good agreement has been found. Meanwhile, dose-weighted lineal energy spectra, frequency averaged lineal energy values and dose averaged lineal energy values of carbon ion with energy from 120 to 430 MeV/u were calculated,too. The frequency averaged lineal energy values are from 185 to 28.3 keV/m while the dose averaged lineal energy values are from 272 to 64.1 keV/m. These studies are useful for treatment plan in carbon ion radiotherapy.     

HIAF高能辐照终端感生放射性

本工作是基于蒙特卡罗模拟软件FLUKA对高能强流重离子加速器（HIAF）高能辐照终端感生放射性进行初步研究。该终端可运行质子最高能量为9.3 GeV,最大流强是1.45×1012 pps（particle per second）。研究内容包括:（1）预测高能辐照终端内活化物质的放射性活度特性;（2）预测不同冷却时间高能辐照终端内残余剂量率分布。研究结果表明,HIAF正常运行时高能辐照终端内的感生放射性主要受束流垃圾桶活化产生的放射性核素影响。当加速器连续运行100天冷却4小时,垃圾桶表面残余剂量率为2.375 mSv·h-1。终端内空气中13N和15O动态饱和比浓度大于其对应的导出空气浓度。冷却水中13N和15O的活度大于对应的ALI_min。该研究是HIAF辐射防护基础研究以及加速器环境影响评价的一项重要内容。The Monte Carlo code FLUKA was used to predict the induced radioactivity of high-energy irradiation terminal of HIAF. The maximum energy of proton is 9.3 GeV, and the maximum current is 1.45×1012 pps (particle per second). In this study we were to predict:(1) the activity properties of activated substances in the experimental terminal; (2) the residual dose rate distribution in the experimental terminal at different cooling time. The results indicate that the induced radioactivity in the high energy irradiation terminal of the HIAF is mainly affected by the radionuclide induced in the beam dump. The residual dose rate on the surface of the beam dump is 2.375 mSv·h-1, after 100 d irradiation and 4 h cooling. The dynamic saturation ratio of 13N and 15O induced in the air inside the terminal is higher than its corresponding derived air concentration. The activity of 13 N and15O induced in cooling water is higher than its ALI_min. This study is a part of radiation protection basic research and environmental impact assessment for HIAF.     

HIAF BRing及高能外靶实验终端的辐射屏蔽设计

强流重离子加速器（HIAF）是中国科学院近代物理研究所自主研制的一台高能强流重离子加速器,它可以实现p到U的全离子加速。为了保证HIAF运行时的辐射安全,针对该装置的增强器（BRing）及高能外靶实验终端,利用蒙特卡洛程序FLUKA及外推法计算得到了加速p,C及U三种离子时所需的辐射屏蔽。结果表明,加速质子时所需屏蔽厚度最大,并以此为依据给出了全地下结构的屏蔽设计。在此基础上,提出了一种估算高能质子/重离子加速器束流均匀损失时横向屏蔽厚度的方法。结果显示,估算结果与FLUKA计算结果符合较好,验证了该方法的有效性和准确性。High Intensity heavy-ion Accelerator Facility (HIAF) is designed by the Institute of Modern Physics, Chinese Academy of Sciences, which can accelerate particles from proton up to uranium. To guarantee the radiation safety of HIAF during operation, the FLUKA code and extrapolation method were adopted to calculate the shielding thickness. The calculations were based on proton, carbon and uranium particles when losing on the Booster Ring (BRing) and the high-energy experimental terminal. The results indicate that the shielding thickness required for accelerating protons was the largest. Basing on the results, a method for estimating the lateral shielding of a high-energy proton/heavy-ion accelerator was proposed. A good agreement shows between the estimated results and the FLUKA calculated results, the validity and accuracy of the method were verified.     

Monte Carlo simulation of carbon ion radiotherapy for the human eye

Carbon ion is the mostly common used particle in heavy ion radiotherapy. In this paper, the carbon ion dose in tumor treatment for human eye was calculated with FLUKA code. An 80 MeV/u carbon beam was irradiated into the human eye from two directions. The first was from the lateral-forward direction, which was a typical therapeutic condition. In this case, a maximum dose was deposited in the tumor volume. In the second a beam was irradiated into eyes from the forward direction to simulate a patient gazing directly into treatment beam during therapy, which may cause a certain medical accident. This method can be used for a treatment plan in heavy ion radiotherapy.     

用MCNPx程序计算宽能谱中子雷姆仪的响应曲线

利用MCNPx程序计算了宽能谱中子雷姆仪的响应曲线。计算表明,增加铅层对低能中子的响应没有明显的影响,但在高能区(几百MeV以上)宽能谱中子雷姆仪的响应与铅层的厚度有关。铅层厚度为0．6cm时响应比普通雷姆仪提高约3倍,当铅层厚度增加到1．2cm时响应高约5倍。虽然计算结果与ICRP建议书中的H^*(10)曲线相比还有一定的差别,但改变慢化体的结构对提高高能中子的探测效率是有明显效果的。The responses of two extended neutron rein counters as function of neutron energy was ca1cuated Monte Carlo code,MCNPx,was applied in the calculations．Isotropic neutron incidence was employed．The results show that the neutron response is independent on thickness of lead 1aver at low energies,and it is clearly increased with thickness of lead layer at high energies．Although tt1e shape of the response curve does not completely agree with the H (10) curve in ICRP 74 report ,the resuhs obtained give good bases for the practical use of the new instrument in high—energy neutron fields