Evaluation of neutron beam characteristics for D-BNCT01 facility

An accelerator-based Boron Neutron Capture Therapy(AB-BNCT)experimental facility called D-BNCT01 has been recently completed and is currently able to generate a high-intensity neutron beam for BNCTrelated research.In this study,we perform several experiments involving water phantoms to validate the Monte Carlo simulation results and analyze the neutron beam characteristics.According to our measurements,D-BNCT01 can generate a neutron flux about 1.2×10^(8)n/cm^(2)/s at the beam port using a 5 kW proton beam.Our results also show that the thermal neutron flux depth distribution inside the water phantom is in good agreement with simulations.We conclude that D-BNCT01 may be effectively employed for BNCT research.

Compact lithium-glass neutron beam monitor for SANS at CSNS

A small-angle scattering neutron spectrometer for material research is under construction at the China Spallation Neutron Source. An intervening neutron beam monitor behind the sample is needed to measure the beam intensity in order to reduce the measurement uncertainty caused by beam fluctuation. Considering the mobility requirement and limited space, we proposed a compact monitor using a type of lithium-glass scintillator provided by China Building Materials Academy. Its performance was studied experimentally using ^(252)Cf and ^(60)Co sources.The neutron light yield of the selected scintillator was measured to be 5:3 × 10~3 photons/neutron. The feasibility of n-gamma discrimination using the charge comparison method was verified. By using the Geant4 toolkit, themonitor was modeled with precise physical processes including neutron tracking, scintillation, and optical photon transmission. The gamma sensitivity and detection efficiency were investigated in the simulation. It was concluded that a 0.5-mm-thick lithium-glass scintillator with natural lithium is an appropriate choice to satisfy both the neutron detection efficiency and gamma elimination requirements.

Nondestructive technique for identifying nuclides using neutron resonance transmission analysis at CSNS Back-n

Nondestructive and noninvasive neutron assays are essential applications of neutron techniques.Neutron resonance transmission analysis(NRTA)is a powerful nondestructive method for investigating the elemental composition of an object.The back-streaming neutron line(Back-n)is a newly built time-of-flight facility at the China Spallation Neutron Source(CSNS)that provides neutrons in the eV to 300 MeV range.A feasibility study of the NRTA method for nuclide identification was conducted at the CSNS Back-n via two test experiments.The results demonstrate that it is feasible to identify different elements and isotopes in samples using the NRTA method at Back-n.This study reveals its potential future applications.

Neutron beam monitor based on a boron-coated GEM

A new thermal neutron beam monitor with a Gas Electron Multiplier （GEM） is developed to meet the needs of the next generation of neutron facilities. A prototype chamber has been constructed with two 100 mm×100 mm GEM foils. Enriched boron-10 is coated on one surface of the aluminum cathode plate as the neutron convertor. 96 channel pads with an area of 8 mm×8 mm each are used for fast signal readout. In order to study the basic characteristics of a boron-coated GEM, several irradiation tests were carried out with of source ^239pu and neutron source ^241Am（Be）. The signal induced by the neutron source has a high signal-to-noise ratio. A clear image obtained from of source ^239pu is presented, which shows that the neutron beam monitor based on a boron-coated GEM has a good two-dimensional imaging ability.

Simulation study on the boron-coated GEM neutron beam monitor

A Monte Carlo method of the 3D GEM simulation is introduced.The physical process of the neutron detection is described with the Geant4 code and the Garfield code.The results of the optimized electric-fields,the emitted ions spectrum,the electrons transverse diffusion and the signal width are presented.Moreover,the preliminary result with a CF-252 neutron source is reported.These are useful in designing detector structures and to provide an optimized option for the development of the boron-coated GEM neutron beam monitor.

Mechanical research and development of a monocrystalline silicon neutron beam window for CSNS

The monocrystalline silicon neutron beam window is one of the key components of a neutron spectrom- eter. Monocrystalline silicon is brittle and its strength is generally described by a Weibull distribution due to the material inhomogeneity. The window is designed not simply according to the mean strength but also according to the survival rate. The total stress of the window is stress-linearized into a combination of membrane stress and bending stress by finite element analysis. The window is a thin circular plate, so bending deformation is the main cause of failure and tensile deformation is secondary and negligible. Based on the Weibull distribution of bending strength of monocrystalline silicon, the optimized neutron beam window is designed to be 1.5 mm thick. Its survival rate is 0.9994 and its transmittance is 0.98447, which meets both physical and mechanical requirements.

Neutron penetration in labyrinths under different beam losses

Multiple analytical methods and Monte Carlo simulations were performed to evaluate neutron penetration in straight and curved labyrinths. Factors studied included variations in beam losses of off-axis point source,on-axis point source,and line source. For the straight labyrinth, it was found that the analytical expressions neglect the dose rate platform appearing at the bend of the labyrinth, and the agreement between analytical methods and Monte Carlo estimation was related to the type of neutron source term. For the curved labyrinth, the neutron attenuation length obtained under different conditions was nearly identical and appeared to be in quite good accord with the empirical formula calculation. Moreover, the neutron energy spectra along the centerline distance of the labyrinth were also analyzed. In the first leg, differences in beam loss led to variance in the distribution of spectra,while in the second and subsequent legs, the spectra were similar, where the main contributors were thermal neutrons. This work is valuable for practical design of the labyrinths in the accelerator facilities.

Target optimization for a 10-MeV E-beam neutron converter

Accelerator-based target design and optimization is an approach for neutron generation. The target plays an important role for a neutron source on an electron accelerator. For optimizing a neutron source using 10 MeV electron beams of Rhodotron-TT200, Pb, Ta, or W alloys with Be were calculated as photo-neutron converter. The neutron yield, flux and energy were simulated using the MCNPX code. The results indicate that a 10 MeV electron beam is capable of producing high-intensity neutron flux of 1013n·cm–2·s–1 with average energy of 0.8 MeV.

中国散裂中子源伴生质子辐照实验平台及其技术参数的确定

为了利用负氢离子加速器中伴随产生的质子成分,中国散裂中子源(China Spallation Neutron Source,CSNS)在直线加速器末端建设了伴生质子辐照实验平台(associated protons experimental platform,APEP)。为了确定其性能参数,采用散射测量、束斑照相、同位素活化法等实验方法对伴生质子辐照实验平台的主要参数进行了刻度。实验证实,该辐照平台可以提供的质子能量范围为10~80 MeV,束斑分布均匀,束流强度范围为1.2×10^(7)~4.0×10^(9) cm^(-2)·s^(-1)。伴生质子辐照实验平台运行稳定,每年提供超过5000 h的束流时间,可以满足宇航器件可靠性测试、探测器刻度、辐照育种以及材料抗辐照特性测试等多种应用需求。

基于强流脉冲离子束的中子辐照模拟装置及评价技术

依据高能原子辐照与中子辐照的初级离位原子(PKA)能谱相似性,基于TEMP-6M型强流脉冲离子束(HIPIB)系统,研发了一种中子辐照模拟装置,该装置以磁绝缘离子二极管伴生的强流脉冲二次电子束流实现0.1 MeV以上高能离子的高效率中和,获得动能为0.1~1 MeV、脉冲宽度为120~160 ns、脉冲辐照剂量为1012~10^(15)n/cm^(2)的强流脉冲原子或混合束,原子占比为85%~100%。通过辐照缺陷原位差热分析方法,快速确定材料缺陷数量、密度及dpa损伤速率等抗中子辐照性能评价指标。以核级AISI 304奥氏体不锈钢为例,计算PKA相似性定标曲线,采用220~280 keV的C原子等效1.8~2.3 MeV中子进行辐照模拟,调节名义束流能量密度0.5~4 J/cm^(2),实测辐照剂量范围为0.46×10^(13)~8.55×10^(13)n/cm^(2),热分析确定Frenkel缺陷密度为1.99×10^(16)~2.90×10^(17)/cm^(2),外推预测奥氏体不锈钢在1021n/cm^(2)中子剂量条件下的辐照损伤为500 dpa量级,适用于核电厂结构材料60年服役寿期评价需求。

基于新型泳池式研究堆BNCT中子束流装置方案设计研究

本研究基于新型泳池式研究堆设计方案,开展了硼中子俘获治疗(BNCT)能谱可变中子束流装置的初步方案设计。根据新型泳池堆堆芯结构,采用屏蔽体及准直器组合方式,对BNCT的中子慢化层、热中子吸收层、伽马屏蔽层以及中子准直器进行了分析计算及优化,在不增加中子引出束流孔道数量的前提下,实现了超热中子及热中子BNCT束流的切换,通过理论计算分析确定了两种装置的中子束流特性,超热/热中子通量密度、单位快中子剂量、单位光子剂量、热中子通量占比等参数均符合IAEA-TECDOC-1223报告的BNCT推荐参考标准,可用于不同能量需求的硼中子俘获治疗,为新型多功能泳池堆的应用及推广提供了技术支持。

脉冲束流下车载加速器中子源靶传热特性

为了研究不同脉冲束流频率下车载加速器中子源靶的传热特性及其热动态响应,通过调整脉冲束流的频率或脉宽对背部冷却微通道靶的传热性能进行模拟,并通过分析靶内部结构的热沉积分布,探究车载加速器中子源靶的热负载上限以及制约束流的因素。选用能量为2.5 MeV、峰值流强为10 mA的束流开展模拟,结果表明:当束流占空比保持在3%不变时,靶的最高温度呈周期波动,且存在上下包络;随着束流频率的上升,每个脉冲周期内靶的上包络温度逐渐下降,这是由于每个脉冲期间的热冲击下降所导致的;频率上升时,每个周期内加热时间与冷却时间同时缩短,导致其下包络温度在最开始增大后基本保持不变;靶的最高温度随着束流频率增加出现从锂层到中间层钽层的转移。该研究对于车载加速器中子源的束流参数选择和靶冷却设计具有一定的参考价值。

Neutron Capture Therapy (NCT) & In-Hospital Neutron Irradiator (IHNI)——a new technology on binary targeting radiation therapy of cancer

BNCT is finally becoming ＂a new option against cancer＂. The difficulties for its development progress of that firstly is to improve the performance of boron compounds, secondly, it is the requirements of quantification and accuracy upon radiation dosimetry evaluation in clinical trials. Furthermore, that is long anticipation on hospital base neutron sources. It includes dedicated new NCT reactor, accelerator based neutron sources, and isotope source facilities. In ad- dition to reactors, so far, the technology of other types of sources for clinical trials is not yet completely proven. The In- Hospital Neutron lrradiator specially designed for NCT, based on the MNSR successfully developed by China, can be installed inside or near the hospital and operated directly by doctors. The Irradiator has two neutron beams for respective treatment of the shallow and deep tumors. It is expected to initiate operation in the end of this year. It would provide a safe, low cost, and effective treatment tool for the NCT routine application in near future.

中国散裂中子源伴生质子束实验平台及其应用

基于中国散裂中子源(China Spallation Neutron Source,CSNS)建设的伴生质子束实验平台(associated proton beam experiment platform,APEP)主要用于宇航器件及设备的辐照损伤研究。质子能量在10~80 MeV之间连续可调,束流能散小于10%,束斑尺寸和束流流强也能够根据实验需求进行调节。自2021年10月投入运行以来,APEP已经开展了电子元器件辐照损伤实验、探测器标定实验、各类材料辐照损伤研究等百余项多学科实验研究,为我国多学科特别是辐照损伤效应领域的科学研究和应用研究提供了一个重要的质子束实验平台。

Californium-252 neutron brachytherapy combined with external pelvic radiotherapy plus concurrent chemotherapy for cervical cancer: a retrospective clinical study

Background:Cervical cancer is the sixth most common cancer in Chinese women.A standard treatment modal?ity for cervical cancer is the combination of surgery,chemotherapy,external?beam radiotherapy and intracavitary brachytherapy.The aim of this study was to retrospectively assess the long?term treatment outcomes of patients with cervical cancer who were treated with californium?252 neutron brachytherapy combined with external?beam radio?therapy plus concurrent chemotherapy.Methods:We retrospectively analyzed the medical records of 150 patients with primary stages IB?IVB cervical cancer who received neutron brachytherapy combined with external?beam radiotherapy concurrently with cisplatin chemo?therapy.All patients were followed up.Using an actuarial analysis,patient outcomes and treatment?related adverse effects were evaluated and compared.Results:The median overall survival(OS)was 33.2 months.The 3?year progression?free survival rates for patients with stages I–II,III,and IV diseases were 81.0%(68/84),65.0%(39/60),and 0%(0/6),respectively;the 3?year OS rates were 90.5%(76/84),85.0%(51/60),and 16.7%(1/6),respectively.Vaginal bleeding was controlled within the median time of4.0 days.One month after treatment,97.3%of patients achieved short?term local control.The local recurrence rates for patients with stages I–II,III,and IV disease were 4.8%(4/84),11.7%(7/60),and 33.3%(2/6),respectively,and the occurrence rates of distant metastasis were 16.7%(14/84),25.0%(15/60),and 100.0%(6/6),respectively.Cancer stage,tumor size,and lymph node metastasis were identified as prognostic risk factors,but only lymph node metastasis was found to be an independent prognostic factor.The most common adverse effects during treatment were grades 1 and 2 irradiation?related proctitis and radiocystitis.Conclusion:For patients with cervical cancer,neutron brachytherapy combined with external?beam radiotherapy plus concurrent chemotherapy produces a rapid response and greatly improves local control and long?term survival rates with tolerable adverse effects.

中国散裂中子源加速器束流引出调试和束损优化

引出系统是中国散裂中子源快循环同步加速器的核心组成部分,对束流精确打靶和加速器稳定运行具有重要意义。首先,详细介绍了快循环同步加速器的引出系统和束流引出方案,重点介绍了一些引出系统相关的关键技术。其次,对引出束流调试进行深入研究,包括纵向束流调试、横向束流调试、引出束流分布优化等,其中纵向束流调试主要针对8个引出Kicker定时进行精确标定,横向束流调试主要指Lambertson型磁铁、8个Kicker磁铁、高能输运线模式的匹配设置。最后,对引出束流束损进行深入研究和针对性优化,探索引出束流损失的各种来源,对Lambertson型磁铁漏场、引出束团长度、Kicker波形平顶、Kicker波形变化进行深入研究并对一些新的测量方法进行详细论述。同时,对Lambertson型磁铁入口产生超大辐射热点的现象进行深入研究,寻找其产生大量束流损失的根源,并提出最终解决方案,降低引出束流损失和辐射剂量,使其满足加速器运行要求。

基于Bulk MicroMegas探测器的高能中子束空间分布测量

为验证中国原子能科学研究院(CIAE)自研的100 MeV回旋加速器中的高能中子束是否符合设计要求,利用自研的Bulk MicroMegas微结构气体探测器对该加速器中子场的空间分布进行了首次试验测量。首先通过模拟计算得到不同厚度聚乙烯(PE)转化膜对不同能量高能中子的转化效率、反冲质子的动能谱与角通量谱、反冲质子在Bulk MicroMegas气体探测器内的沉积能量谱以及中子与探测器结构物质反应产物占比等;然后利用Bulk MicroMegas探测器测量该回旋加速器产生的高能中子场在不同能量和距离处28个点位的中子通量分布,并根据通量分布计算中子束斑半径。结果表明,Bulk MicroMegas微结构气体探测器可以实现对高能中子场束斑边界成像,中子通量随束斑半径的变化关系符合常见束斑边界拟合函数;束斑半径测量结果与模拟计算结果接近。

遗传算法优化加速器硼中子俘获治疗束流整形设计

基于加速器的硼中子俘获治疗(AB-BNCT)设备是一种基于加速器产生的超热中子的癌症治疗装置,可以建在人口密集地区的医院。BNCT治疗对于中子注量率和各种沾污有严格的要求,为满足这些要求需对中子束流整形装置进行优化设计。本文以14 MeV回旋加速器为基础,研究了一种基于遗传算法的束流整形装置(BSA)的优化设计方案,利用遗传算法对束流整形装置内部材料及尺寸进行设计优化。结果表明,该方法可高效地实现多目标优化设计。该方法经过修改能够用于核工程其他相关领域的设计。

中子皮结构及其在核反应中的效应

中子皮是不稳定原子核中存在的一种奇特结构,在核反应过程中会产生各种效应。不同理论模型研究发现,中子皮厚度会影响核-核碰撞中的中子擦去截面、轻粒子产额比、重碎片产额比、光子产生截面等物理量,也与原子核的集团结构、表面宽度、温度等存在密切关系。在高能重离子碰撞中研究发现,中子皮同样存在明确的效应。实验上,基于放射性核束装置可以产生具有中子皮结构的不稳定核,通过测量其与稳定核发生反应后与中子皮敏感的观测量,能提取或确定中子皮厚度。结合核理论模型,可以进一步约束非对称核物质的状态方程及核天体的相关性质。

瞬发γ射线中子活化分析的现状与发展

概述了瞬发γ射线中子活化分析(PGNAA)的现状与发展,重点介绍了PGNAA的基本原理,国际上已建的PGNAA装置概况、PGNAA方法学中的单比较器k0法和高能γ射线的效率刻度技术,以及PGNAA在新材料、环境样品、生物和药物以及矿物中H、B、N、Cl等轻元素分析测定方面的日益发展的应用状况。此外,还介绍了在中国原子能科学研究院重水研究堆上建立的热中子束PGNAA实验装置。