Cerium-doped lutetium oxyorthosilicate: a fast, efficient newscintillator

The authors discuss a single-crystal inorganic scintillator, cerium-doped lutetium oxyorthosilicate (Lu_2(1-x)Ce_2x (SiO₄) or LSO). It has a scintillation emission intensity which is ~75% of NaI(Tl) with a decay time of ~40 ns. The peak emission wavelength is 420 nm. It has a very high gamma-ray detection efficiency due to its density of 7.4 g/cm³ and its effective atomic number of 66. Its radiation length of 1.14 cm is only slightly longer than bismuth germanate (BGO). The scintillation properties of Ce-doped LSO are compared to NaI(Tl), BGO, and cerium-doped gadolinium oxyorthosilicate (GSO). In addition to desirable physical properties such as high density and high atomic number, LSO also processes a combination of high emission intensity and fast decay which together are superior to any other known single crystal scintillator     

低能电子辐照对环氧树脂性能的影响

为了研究低能电子辐照对环氧树脂的体积电阻率、邵氏硬度、拉伸强度和官能团结构的影响,本文在电子辐照能量为30 keV,注量率1×10¹¹ cm^-2•s^-1,总注量为1.6×10¹⁴ cm^-2,真空度10^-6 Pa条件下,结合国家标准对辐照前、后环氧树脂材料的机械性能和结构进行表征。结果表明,辐照后环氧树脂材料的体积电阻率、邵氏硬度、拉伸强度等宏观物理性能均有下降。傅里叶红外光谱图显示环氧树脂主要官能团强度降低,产生的•H、•OH等自由基与聚合物分子上的羟基与氢结合。研究结果对环氧树脂材料在辐射环境中的使用具有重要意义。     

用于n/γ混合场测量的涂硼电离室研制

研制了一种能同时测量混合场中γ和中子注量率的涂硼电离室,并实验测试了其性能。涂硼电离室由两个大小和结构一致的腔室组成：1个仅对γ灵敏,另1个对γ与中子均灵敏。用强度为2.7×10⁷ s^-1 的Am-Be源测得电离室的中子灵敏度达9.2×10^-16 A/(cm^-2•s^-1),在剂量率为5.24 μGy/h的¹³⁷Cs γ场中,电离室的γ灵敏度达7.36×10^-16 A/(MeV•cm^-2•s^-1)。涂硼电离室I-V曲线坪长为600 V,坪斜小于4%/100 V,在工作电压为-400 V时,其γ补偿修正系数<5%,可用于核设施周围的混合场监测。     

利用测热技术测量核反应堆中子通量密度

一种新型中子探测器被研究,其原理是利用带电离子在矿物中沉积的能量退火时会以热量的方式释放出来,通过测量释放的热量而确定中子通量密度。对新型中子探测器进行刻度,在反应堆内某位置测量的热中子通量密度为5.108×10¹¹ cm^-2•s^-1,与标定的热中子通量密度(5.000×10¹¹ cm^-2•s^-1)在2%内符合,说明该探测器可测量中子通量密度。本文方法制作的探测器体积小,可制作成不同形状,便于反应堆不同环境下的中子通量密度测量。选取相应中子能量反应截面较大的元素,该探测器还可测量不同中子能量的通量密度。     

上升时间法的α/γ波形数字化实时甄别

基于CsI(Tl)探测器的α/γ波形甄别能力,采用上升时间法,设计了一种波形实时甄别系统,系统由高速ADC和高性能FPGA组成。介绍了实时甄别系统的方案设计和甄别算法设计,利用60 Coγ源、241 Amα源对实时系统进行了甄别测试。研究表明:设计的数字化实时波形甄别系统体积小,能实时甄别开α、γ粒子,甄别品质因子为0.687 5,事件计数率可达2.5×105 s-1。     

堆内超临界水回路辐照装置物理参数模拟研究

堆内超临界水回路对我国超临界水堆燃料和结构材料的辐照腐蚀实验具有重要意义,辐照装置位于反应堆堆芯栅格,是超临界水回路的核心部件。采用MCNP程序模拟研究辐照装置的关键物理参数,并考虑超临界水热物特性对物理参数的反馈效应。计算得到辐照装置热中子注量率为4.72×10¹³ cm^-2•s^-1,快中子注量率为1.55×10¹⁴ cm^-2•s^-1,辐照产热率为14.7 kW,反应性引入为0.045%。     

Study of the key factors affecting the triple grid lifetime of the LIPS-300 ion thruster

In order to ascertain the key factors affecting the lifetime of the triple grids in the LIPS-300 ion thruster,the thermal deformation,upstream ion density and component lifetime of the grids are simulated with finite element analysis,fluid simulation and charged-particle tracing simulation methods on the basis of a 1500 h short lifetime test.The key factor affecting the lifetime of the triple grids in the LIPS-300 ion thruster is obtained and analyzed through the test results.The results show that ion sputtering erosion of the grids in 5 kW operation mode is greater than in the case of 3 kW.In 5 kW mode,the decelerator grid shows the most serious corrosion,the accelerator grid shows moderate corrosion,and the screen grid shows the least amount of corrosion.With the serious corrosion of the grids in 5 kW operation mode,the intercept current of the acceleration and deceleration grids increases substantially.Meanwhile,the cold gap between the accelerator grid and the screen grid decreases from 1 mm to 0.7 mm,while the cold gap between the accelerator grid and the decelerator grid increases from 1 mm to 1.25 mm after 1500 h of thruster operation.At equilibrium temperature with 5 k W power,the finite element method(FEM)simulation results show that the hot gap between the screen grid and the accelerator grid reduces to 0.2 mm.Accordingly,the hot gap between the accelerator grid and the decelerator grid increases to 1.5 mm.According to the fluid method,the plasma density simulated in most regions of the discharge chamber is 1?×?10~(18)-8?×?10~(18)m~(-3).The upstream plasma density of the screen grid is in the range 6?×?10~(17)-6?×?10~(18)m~(-3)and displays a parabolic characteristic.The charged particle tracing simulation method results show that the ion beam current without the thermal deformation of triple grids has optimal perveance status.The ion sputtering rates of the accelerator grid hole and the decelerator hole are 5.5?×?10~(-14)kg s~(-1)and 4.28?×?10~(-14)kg s~(-1),respectively,while after the thermal deformation of the triple grids,the ion beam current has over-perveance status.The ion sputtering rates of the accelerator grid hole and the decelerator hole are 1.41?×?10~(-13)kg s~(-1)and 4.1?×?10~(-13)kg s~(-1),respectively.The anode current is a key factor for the triple grid lifetime in situations where the structural strength of the grids does not change with temperature variation.The average sputtering rates of the accelerator grid and the decelerator grid,which were measured during the 1500 h lifetime test in5 k W operating conditions,are 2.2?×?10~(-13)kg s~(-1)and 7.3?×?10~(-13)kg s~(-1),respectively.These results are in accordance with the simulation,and the error comes mainly from the calculation distribution of the upstream plasma density of the grids.     

14 MeV快中子照相准直屏蔽系统的设计与优化

基于强流氘氚中子源科学装置HINEG设计了一套快中子照相准直屏蔽系统。采用中子输运设计与安全评价软件系统SuperMC和ENDF/B-Ⅶ.0数据库计算了准直中子束的中子能谱及注量率、γ射线能谱及注量率、直射中子注量率与γ射线注量率比值（φ_d/φ_γ）、直射与散射中子注量率比值（φ_d/φ_s）、准直束中子注量率的不均匀度等特性参数,并采用MCNP5程序进行了对比验证。研究了准直屏蔽系统的内衬材料、尺寸等对特性参数的影响规律,并通过优化获取了最优设计方案。计算结果显示,在同等计算条件下,SuperMC计算结果与MCNP计算结果相对偏差小于1%,准直屏蔽系统的φ_d/φ_γ为50.1,φ_d/φ_s为5.7,在Φ30 cm视野范围内的中子注量率为4.80×10⁷ cm^-2•s^-1,其中直射中子注量率为4.09×10⁷ cm^-2•s^-1,中子注量率不均匀度为5.8%,满足快中子照相对准直束特性参数的要求。     

Scintillation properties of RbGd2Br7:Ce.Advantages and limitations

The scintillation properties of RbGd₂Br₇ crystals, doped with Ce³⁺ concentrations of 0.02, 0.11, 0.88, 2.05, 4.1, and 9.8%, are studied under X-ray and γ-quanta excitations. For the RbGd₂Br₇ sample doped with 9.8% Ce, the authors measured a light yield of 56000±6000 photons per MeV of absorbed γ-ray energy with a main decay time of 43±1 ns, using a Hamamatsu R1791 photomultiplier (PMT), a ¹³⁷Cs radioactive source, and a shaping time of 10 μs. A time resolution of 790±10 ps was measured for the RbGd₂Br₇:9.8% Ce compound, using BaF₂ as second scintillator, two XP2020Q PMTs, a ²²Na source, and an energy threshold set at E⩾511 keV. With the R1791 PMT, an energy resolution of 4.1% (FWHM over peak position) for the 662-keV full absorption peak has been observed for two crystals of 7×4×2 mm³ and 15×5×1 mm³ with 4.1 and 9.8% Ce content, respectively. Moreover, the nonproportional responses of three RbGd₂Br₇:Ce compounds with different concentrations (0.11, 2.05, and 9.8%) were studied revealing an almost-constant light output response from 17.4 keV to 1 MeV. These properties are compared to three other well-known scintillators: NaI:Tl, CsI:Tl, and Lu₂SiO₅:Ce     

无机闪烁探测器综述

主要介绍了无机闪烁探测器的发展和现状.包括对常用无机闪烁晶体NaI(Tl)、CsI(Na)、CsI(Tl)、CsI(Pure)、BaF2、BGO、CdWO4、GSO:Ce和YAP:Ce等的密度、等效原子序数、衰减时间、光输出、发射光谱、能量分辨率、温度特性、辐射性能、加工性能等方面的介绍,以及对Ce3 掺杂的新型闪烁体的特性及发展前景的介绍.旨在为读者选择、使用无机闪烁晶体提供一份参考.     

Radiation damage in undoped CsI and CsI (Tl)

Radiation damage in undoped CsI and CsI(Tl) crystals using ⁶⁰ Co gamma radiation for doses up to ~4.2×10⁶ has been studied. Samples from various manufacturers were measured, ranging in size from 2.54-cm-long cylinders to a 30-cm-long block. Measurements were made on the change in optical transmission and scintillation light output as a function of dose. Although some samples showed a small change in transmission, a significant change in light output was observed for all samples. Recovery from damage was also studied as a function of time and exposure to UV light. A short-lived phosphorescence was observed in undoped CsI, similar to the phosphorescence seen in CsI(Tl)     

Large-area APDs and monolithic APD arrays

In this paper, development of large-area planar avalanche photodiodes (APDs) and monolithic APD arrays for X-ray and scintillation detection is discussed. Single APDs with areas as large as 10 cm² have been fabricated and tested with a CsI(Tl) scintillator (3.8 cm diameter, 2.5 cm height). The resolution of the 662 keV photopeak has been measured to be 9% (FWHM). The X-ray detection performance, gain, and noise of these large APDs have been characterized. Multielement APD arrays have also been fabricated in various formats, such as 4×4 to 14×14 elements (2 mm pixels), and the uniformity of gain, noise, and sensitivity has been evaluated for 4×4 arrays using an ⁵⁵Fe source. Timing properties have been measured. Packaging issues related to the APD arrays are discussed     

Preparation of High Specific Activity Strontium-89 Solution in High Flux Engineering Test Reactor

⁸⁹SrCl₂ is an important radioactive drug for the bone metastasis. It is included in the new pharmacopoeia in 2015 and has a promising future in the market. Depending on the high flux engineering test reactor(HFETR), the process of preparation of high specific activity⁸⁹SrCl₂ solution by nuclear reaction ⁸⁸Sr(n, γ)⁸⁹Sr was studied. High purity enriched⁸⁸SrCO₃ was used as target material and irradiated for 56 days under the condition of thermal neutron fluence rate about 2×10¹⁴ n•cm^-2•s^-1. After dissolution and filtration, the colorless⁸⁹SrCl2 solution was obtained. The specific activity of⁸⁹SrCl₂ solution was 7.77×10⁹-1.08×10¹⁰ Bq•g^-1, the activity concentration was 3.59×10⁸-1.21×10⁹ Bq•mL^-1, the gamma impurity content was 0.11%-0.14%, the Al impurity content was much lower than 2 μg•mL^-1(activity concentration 7.4×10⁷ Bq• mL^-1).⁸⁹SrCl₂ solution had been tested to meet the requirements of the industry and could be used as raw material for the production of injection. The development of single 7.4×10¹⁰ Bq level preparation device of high purity and high specific activity of ⁸⁹Sr had been finished. This research is important for localization of isotope products.     

溶液中钚α活度的直接测量研究

选取YAP∶Ce闪烁体作为仪器核心部件,建立了接触式测量溶液中微量、痕量钚α活度的分析方法。结果表明:水相钚溶液浓度在5.20×10-5~1.30×10-3 g/L范围内线性良好(R2=0.987 7),定量检测下限为5.20×10-5 g/L;有机相钚溶液浓度在2.27×10-5~1.13×10-3 g/L范围内线性良好(R2=0.992 3),定量检测下限为2.27×10-5 g/L。本分析方法有别于传统的α计数法,过程无需制源,操作简单、方便,有望为后处理工艺过程中微量和痕量钚的在线或实验室分析提供一种新的途径。     

利用HFETR制备有载体177Lu

¹⁷⁷Lu是一种优良的诊疗一体化医用放射性核素,其标记的放射性药物被广泛用于多种癌症的诊断和治疗。其中,有载体¹⁷⁷Lu的制备具有放射化学处理简单、¹⁷⁷Lu产量高等优点。为此,在高通量工程试验堆(HFETR)中利用热中子辐照¹⁷⁶Lu,开展有载体¹⁷⁷Lu的制备研究。本研究分别辐照天然Lu和富集¹⁷⁶Lu进行热实验验证,结果表明：天然Lu在2×10¹⁴ n·cm^-2·s^-1热中子通量下辐照13 d,生成¹⁷⁷Lu比活度约为0.87 Ci/mg,^177mLu杂质含量为0.009%;富集(86.5%)¹⁷⁶Lu在热中子注量率为1×10¹⁴ n·cm^-2·s^-1条件下辐照28 d,生成¹⁷⁷Lu比活度约为24.9 Ci/mg,^177m...     

BRISOL钠同位素放射性核束的产生

北京放射性核束装置在线同位素分离器（BRISOL）采用100 MeV、200 μA回旋加速器提供的质子束打靶产生中、短寿命放射性核束,在线分析后供物理用户使用,其质量分辨率好于20 000。为开展²⁰Na核的奇异衰变特性研究,研制了氧化镁靶,并采用100 MeV质子束轰击氧化镁靶在线产生了^20～26Na⁺的钠同位素放射性核束。当质子束流强为8 μA时,²⁰Na⁺离子束的最大产额为2×10⁵ s^-1,²¹Na⁺离子束的最大产额为4×10⁸ s^-1。完成了北京放射性核束装置首个放射性核束物理实验,累计供束近200 h。     

磷酸二丁酯在2.0 mol/L HNO3介质中的水解动力学

通过红外光谱、气质联用和离子色谱等分析方法确定了磷酸二丁酯在后处理常见工况2.0 mol/L HNO₃下的反应产物主要为丁醇、丁酸、丙酸、磷酸一丁酯和磷酸根离子等。采用离子色谱定量分析测定了磷酸一丁酯和磷酸根离子的浓度与反应时间和温度的关系,计算了磷酸二丁酯水解反应的速率常数,并对测定数据进行了计算拟合。结果表明：在110~150 ℃范围内,磷酸二丁酯的水解速率随温度的升高呈指数增长,满足准一级反应动力学方程;110 ℃和150 ℃的一级水解速率常数分别为6.30×10^-3 s^-1和2.10×10^-1 s^-1,二级水解速率常数分别为3.10×10^-3 s^-1和1.98×10^-1 s^-1;一级水解反应的指前因子为9.38×10¹² s^-1,对应的活化能为111.0 kJ/mol,二级水解反应的指前因子为1.09×10¹⁶ s^-1,对应的活化能为135.2 kJ/mol。动力学计算值与实验值的误差在±9%以内。     

Neutron-induced radiation damage in silicon detectors

Ion-implanted silicon pad detectors fabricated on different n-type and p-type silicon wafers with initial resistivities between 2.6 and 12.9 kΩcm were irradiated with neutrons of ~1 MeV energy, up to a fluence of 5×10¹³ n cm^-2. The evolution of diode leakage current and capacitance characteristics is presented as a function of the neutron fluence. The reverse diode current increases proportionally to the neutron fluence. There is evidence that the doping of the initial n-type material evolves towards intrinsic and inverts to an apparent p-type at fluences between 1×10¹³ and 3×10¹³ n cm^-2, depending on the initial silicon resistivity. There is also evidence that p-type material remains of the same conduction type with a slight increase of the acceptor doping with fluence. The signal shape and the charge collection efficiency for incident β particles were measured     

医院中子照射器中子束流出口处热中子注量率的测量

医院中子照射器是基于微型反应堆而设计的专门用于硼中子俘获治疗（BNCT）的核反应堆装置,其额定功率为30 kW。在堆芯相对两侧分别设有一条热中子束流和超热中子束流用于病人照射,在热中子束流内引出一条实验用热中子束流,用于瞬发γ法测量病人血硼浓度。本工作利用²³⁵U裂变靶和白云母探测片测量了热、超热和实验用热中子束流出口处的热中子绝对注量率。结果显示,在30 kW额定功率运行时,热、超热和实验用热中子束流出口处的热中子注量率分别为1.67×10⁹、2.44×10⁷和3.03×10⁶ cm^-2•s^-1。以上结果达到了BNCT设计要求,并能满足瞬发γ测量血硼浓度的要求。