Effect of gamma and lead as an additive material on the resistance and strength of concrete

Nowadays, concrete is extensively used for transporting, storing radioactive wastes and as a shield in nuclear planets. For this purpose, concrete must have a certain property like density in particular. Several of the specimens were produced to examine the effect of gamma radiation on compressive strength of concrete during solidification. The results show that the strength of gamma radiated concrete specimens has greatly been increased and it has been confirmed by perceiving their microstructure using scanning electron microscope (SEM).In another section, concrete is mixed with different percentages of lead to study gamma-ray shielding properties. By comparing obtained data from concrete specimens with and without lead, it was observed that, if the powder of lead with 90% ratio of lead-to-cement by weight is added in concrete mixture, the compressive strength of concrete reaches a maximum value and concrete can be a suitable shield against gamma-ray.     

Calculation of Energy Deposition Spectra for Radioactivity Induced in Germanium Gamma-Ray Spectrometers by Various Space Environments

Radioactivity induced in detector materials by cosmic rays and radiation belt protons provides an ultimate limit to the sensitivity of gamma-ray spectrometers used for gamma-ray astronomy and remote sensing spectroscopy of planetary bodies. The increasing use of high resolution germanium spectrometers has made it worthwhile to adapt predictive techniques for this component based on those previously used for alkali halide scintillators. Decay rates of the most significant radionuclides have been calculated using semiempirical cross-sections and combined with Monte Carlo calculations of energy depositions to yield background spectra for both interplanetary space and low earth orbit locations.     

Using gamma-gamma coincidence measurements to validate Monte Carlo generated detector response functions

Monte Carlo simulation of gamma-ray transport for the purpose of performing elemental analysis of bulk samples requires the tracking of gamma rays in the sample and also in the detector(s) used. Detector response functions (DRF’s) are an efficient and accurate variance reduction technique that greatly decreases the simulation time by substituting the tracking of gamma rays inside the detector by predefined single energy gamma-ray spectra. These spectra correspond to the average response of the detector for incident gamma rays.DRF’s are generated by Monte Carlo methods and are benchmarked with experimental data. In this work, prompt gamma-gamma coincidence measurements are presented as a way to validate DRF’s for high-energy gamma rays.     

铅和混凝土中宽束医用X、γ射线透射曲线的拟合方程

根据国际放射防护委员会（ICRP）给出的屏蔽材料铅和混凝土中宽束医用X、γ射线的透射曲线,采用自编的曲线拟合计算机程序得到了相应曲线的拟合方程;由此导出ICRP推荐值相一致的十分之一值厚度;计算了医用X射线装置典型工作负荷下,与源不同距离时对于初级X射线的屏蔽厚度,结果与相同条件下ICRP的参考值差别大多在10%以下。     

CARR堆冷中子瞬发伽玛活化分析系统及实验研究

利用中国先进研究堆（CARR）在国内首次开展了冷中子瞬发伽玛活化分析（CNPGAA）实验,采用定制加长的电制冷高纯锗（HPGe）探测器和先进的数字多道谱仪DSPEC®-502进行测量,获得了NH₄Cl样品中元素冷中子瞬发伽玛谱和本底谱等数据,同时利用伽玛放射源¹⁵²Eu、¹³⁷Cs、⁶⁰Co以及NH₄Cl产生的瞬发伽玛射线对探测器在宽能区0.1~8 MeV进行能量刻度。为降低环境辐射本底,HPGe探测器外围采用环形锗酸铋（BGO）康普顿谱仪,10 cm铅以及含⁶Li和¹⁰B材料对中子束流准直屏蔽。此外,利用金片活化法测量了CARR堆运行功率为15 MW时有无冷源情况下冷中子导管B(CNGB)末端1 m处的中子注量率,结果显示有冷源时中子注量率可提高一个量级。     

Calculations of the transport of neutrons and secondary gamma rays through concrete for incident neutrons in the energy range 15 to 75 MeV

Earlier work by Alsmiller et al. considered coupled neutron and secondary-gamma-ray transport through a thick shield of silicon dioxide with 5% water by weight for neutron sources with energies of 50, 100, 200, 300 and 400 MeV. In that work, the approximation was made that gamma rays were produced only by neutron capture. In the present work, coupled neutron and secondary-gamma-ray transport through a thick shield of concrete for neutron sources with energies of 15, 25 and 75 MeV is considered. In this study, gamma-ray production for all interactions involving neutrons with energies up to 15 MeV was included; i.e., the approximation made here is that gamma-ray production can be neglected for interactions by neutrons with energies > 15 MeV.For incident neutron energies of 15, 25, 50, and 75 MeV, results of total and gamma-ray dose equivalents are given as a function of depth into the slab. For the 50- and 75-MeV incident neutron energies, the gamma-ray dose equivalent was found to be no more than 5% of the total dose equivalent at all depths considered ( 1500 g/cm²). For the 15- and 25-MeV incident neutron energies, however, the gamma-ray dose equivalent dominates at greater depths into the slab. A conservative estimate of the effect of including gamma rays produced in interactions with neutrons of energies > 15 MeV indicates that the calculated total dose equivalent would increase by no more than 5%.     

Study of relation between the gamma flux buildup factors and source geometry by M-C simulation

This paper is to achieve a gamma-ray source with the lowest rate of buildup factor, which is of great importance in medical, industrial and agricultural sciences.The flux buildup factor of gamma rays is calculated by the MCNP code for point, linear, surface and volume sources with shield layers of lead, iron and aluminum. The results show that for the high Z shielding material, the flux buildup factor of coaxial cylindrical sources is the lowest(1.6–2.3)of all sources, while for low Z shielding materials, the coaxial disk surface sources have smaller buildup factor(1.45–1.6).     

Prompt Gamma-Ray Analysis of Steel Slag in Concrete

Blast furnace slag (BFS) is added to Portland cement concrete to increase its durability, particularly its corrosion resistance. Monitoring the concentration of BFS in concrete for quality control purposes is desired. In this study, the concentration of BFS in concrete was measured by utilizing an accelerator-based prompt gamma-ray neutron activation analysis (PGNAA) setup. The optimum size of the BFS cement concrete specimen that produces the maximum intensity of gamma rays at the detector location was calculated through Monte Carlo simulations. The simulation results were experimentally validated through the gamma-ray yield measurement from BFS cement concrete specimens having different radii. The concentration of BFS in the cement concrete specimens was assessed through calcium and silicon gammaray yield measurement from cement concrete specimens containing 5 to 80 wt% BFS. The yield of calcium gamma rays decreases with increasing BFS concentration in concrete while the yield of silicon gamma rays increases with increasing BFS concentration in concrete. The calcium-to-silicon gamma-ray yield ratio has an inverse relation with BFS concentration in concrete.     

FNS-100正比计数器用于测量快中子场能谱时的干扰分析

为了了解FNS-100正比计数器用于测量快中子场能谱时干扰信号的特性,本文计算分析了60Co产生的低能γ射线以及7 MeV和10 MeV的高能γ射线所产生的干扰,同时模拟了反冲3He核、反冲质子在该正比计数器中产生的干扰影响.计算结果表明,γ射线对快中子能谱测量几乎没有影响,而反冲3He核和反冲质子存在比较大的影响.     

Investigations of the SAD design parameters for optimum experimental performance

A project of fast experimental accelerator driven system called SAD – Subcritical Assembly in Dubna – containing MOX fuel and driven by 660 MeV proton beam is described and analysed. It is shown by design calculations that the necessity exists for certain modifications, allowing for better reliability of measurements of system time characteristics. Different solutions such as: cadmium separation of the biological concrete shield, admixtures of B₂O₃ to the concrete and certain slowing down of neutrons were analysed. Experiments on a bare spallation targets were conducted and the production of radionuclides in the lead target were measured and compared with calculations.     

高纯锗探测器探测效率研究

利用系列标准γ射线源对高纯锗探测器的探测效率进行了各种测量,与蒙特卡罗计算程序相结合,对于高纯锗探测效率进行了分析和讨论.计算效率与测量效率在4%以内吻合.在一定探测距离条件下面源与点源的探测效率在1%以内吻合,而且面源的自吸收可以用平行束在材料中的自吸收来计算;当面源靠近探测器时,由于γ射线的倾斜入射,这种方法就不适用了,需要用蒙特卡罗方法进行自吸收较正.     

Gamma-ray spectral penetrations: A review

This review discusses gamma-ray penetration through matter, particularly the differential, angular and energy spectra which have been reported. Experimental spectra are obtained by unfolding measured data and the features of unfolding methods and codes are discussed. A large proportion of the published data is for point and parallel beam sources of gamma radiation from the decay of the isotopes ¹³⁷Cs and ⁶⁰Co. Data for higher energy sources show the importance of secondary radiations of Bremsstrahlung and positron annihilation photons in shield penetrations. Reasons why it is difficult to make direct comparisons of reported data are outlined. The need for benchmarking methodology is emphasized.     

BRISOL钾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）采用一台100 MeV回旋加速器提供的最大200 μA的质子束打靶在线产生放射性核束,其最高质量分辨率好于20 000。2015年,BRISOL装置建成并使用05 μA质子束轰击氧化钙靶产生了37K+、38K+放射性核束,其中38K+的产额为1×106 pps。为了提高氧化钙靶产生钾放射性核束的产额以满足物理用户需求,BRISOL于近期开展了氧化钙靶的在线实验。实验中使用氧化钙靶产生了36～38K+、43K+、45～47K+等多种放射性核束,同时将38K+的最大产额提高到了112×1010 pps。本文详细介绍氧化钙靶的研制及在线实验结果。     

Measurement of nitrogen depth profile in steel

The characterization of nitridated steel samples, in special the depth profile of nitrogen, aims to help improving the quality of the surface and to increase the durability of the steel pieces. In this work we used ERDA and NRA to determinate the profile of nitrogen in different sets of stainless steel samples. An incident beam of ³⁵Cl of 56 MeV was used for ERDA analysis of a first set of samples. Results indicated an homogeneous distribution for most of the identified elements, with atomic nitrogen concentrations around 2% in the analyzed depth range (0.2 μm) and the presence of thin films on the surface (about 50 × 10¹⁵ at/cm²), one of C and the other of iron oxide. In a second set of samples, 4.43 MeV gamma rays produced from ¹⁵N(H,αγ)¹²C reaction, using an external proton beam of 1.3 MeV, were used to quantify nitrogen concentration. N concentrations of about 0.47% were obtained comparing the gamma production rate of the samples with a referenced material (Stainless steel CRM298 - 0.236% of N in mass) irradiated in the same conditions. Also PIXE analyses were done on both sets of samples in order to identify main elements in the matrix.     

在线同位素分离器靶-源中靶材料的放射性活度

用LCS+CBURN程序计算在线同位素分离器靶-源中铅、钨、铜、铝、石墨靶材料以及结构材料水、不锈钢在100MeV、200μA强流质子束照射下所产生的放射性核素活度以及γ射线强度随时间的变化,以便为靶的设计、更换以及后期处理提供一定的设计依据。所选靶材料在照射后会产生长寿命放射性核素氚,其中,铅靶材料中还会产生¹³¹I。     

Measurements of keV-neutron capture cross sections and capture gamma-ray spectra of 105Pd

The neutron capture cross sections and capture gamma-ray spectra of ¹⁰⁵Pd were measured in the region from 15 to 100 keV and at 585 keV. A neutron time-of-flight method was utilised with an anti-Compton NaI(Tl) spectrometer and a 1.5-ns pulsed neutron source by the ⁷Li(p,n)⁷Be reaction. The capture yields were obtained by applying a pulse-height weighting technique to the observed net capture gamma-ray pulse-height spectra. The capture cross sections of ¹⁰⁵Pd were derived with errors less than 5%, using the standard capture cross sections of ¹⁹⁷Au. The evaluated capture cross sections of JENDL-4.0 and ENDF/B-VII.1 were compared with the present results. The evaluations of JENDL-4.0 and ENDF/B-VII.1 were larger than the present results by 3%–15% in the region from 15 to 100 keV and at 585 keV. The capture gamma-ray spectra of ¹⁰⁵Pd were also derived by unfolding the observed net capture gamma-ray pulse-height spectra. The multiplicities of capture gamma rays of ¹⁰⁵Pd were obtained from the capture gamma-ray spectra.     

Similarity in Pressure Dependence among Separation Factors of Thermal Diffusion Column in Total-Reflux Operation

Research on laser Compton scattering gamma-ray-based nuclear transmutation has been carried out to identify a method of reducing the hazards of long-lifetime radioactivity of nuclear waste. To study the photonuclear reaction experimentally, a laser Compton scattering gamma-ray facility was built on a storage ring at NewSUBARU and ~17MeV gamma-ray photons were produced. An investigation on the reaction rate of radioactive iodine waste was carried out. Based on the characteristics of laser Compton scattering gamma rays, a cylindrical target was adopted for the irradiation experiment. The radioactivity of the irradiated target was measured and the transmutation reaction rate was deduced. Experimental results were close to simulation findings.     

Resolution and sensitivity as a function of energy and incident geometry for germanium detectors

The use of modeling programs such as MCNP to predict the response of HPGe detectors is increasing in importance. Accurate simulation of germanium detectors to incident gamma rays relies on knowledge of the performance of the detector in different detector–source geometries. Two important performance parameters are the resolution and sensitivity. The resolution is the FWHM and FW.1M/FWHM ratio. The IEEE 325-1996 standard only specifies the FWHM measurement at one geometry and two energies. Nearly all measurements are made in a different geometry and at other energies. Other investigators [Specifications for Today’s Coaxial HPGe Detectors, 2001 ANS Annual Meeting, Milwaukee, WI; Metzger, private communication, see also: Radionuclide Depth Distribution by Collimated Spectroscopy, 2002 ANS Topical Meeting, Santa Fe, NM], have shown that the sensitivity and resolution change with position of the incident gamma ray on the front of the detector. Such variability has possible implications for the accuracy of peak shape and area determination, since the calibration is potentially a function of angle of incidence. To quantify the sensitivity and resolution variation as a function of energy and point of incidence, measurements have been made on several coaxial detectors of various crystal types and sizes in different source–detector geometries. The full-energy peaks from 59 keV to 2.6 MeV were used. The detectors were placed in a low-background shield to reduce any contribution from external sources. None of the detectors tested was a low-background type. The sources used were an ²⁴¹Am source, ⁶⁰Co source and a natural thorium oxide sample. The ²⁴¹Am 59 keV gamma rays were collimated by a 2 cm thick, 1 mm diameter lead collimator. Several gamma rays from the thorium source were used and collimated by a 10 cm thick and 2 mm diameter tungsten collimator. These collimated sources were used to collect spectra for the incident beam on the front and sides of the detectors. The peak widths were calculated using the methods outlined in IEEE 325-1996. Data are presented to show that the peak shape and sensitivity change with incident beam position and full peak energy.     

Characterization of the new scintillator Cs_2LiYCl_6:Ce~(3+)

The first domestic inorganic scintillator, Cs_2LiYCl_6:Ce~(3+)(CLYC), was grown at Beijing Glass Research Institute using the vertical Bridgman method. In this work, we evaluated the performance of this new CLYC crystal in terms of its gamma-ray energy resolution and pulse shape discrimination(PSD) capability between neutrons and gamma rays. The decay times associated with different scintillation mechanisms were obtained by fitting decay functions to the neutron and gamma-ray waveform structures. We found an energy resolution of * 4.5% for 662-ke V gamma rays and efficient neutron/gamma PSD with a figure of merit of * 2.6. Under gamma-ray excitation, there is an ultrafast scintillation mechanism in CLYC with a decay time of approximately 2 ns, whereas there is no evidence of ultrafast decay under thermal neutron excitation. This work contributes to the promotion of domestic development of CLYC.     

Gamma-ray and half-life data for the fission products

Presented here are gamma-ray and half-life data for the fission products. The first table lists the energies and intensities of up to 5 of the more abundant gamma rays for each fission product. The second table lists gamma rays in order of increasing energy. The first section of this table covers nuclides with half-life less than one hour. The second section covers nuclides with half-life greater than one hour. Each listing consists of gamma-ray energy, intensity, and half-life. The third table lists all the fission products in order of increasing mass. Data for each nuclide include half-life, uncertainty and reference key for half-life, number of gamma rays, reference key for gamma data, total gamma-decay energy (including internal-conversion energy), and internal-conversion energy expressed as fraction of total gamma-decay energy.References available through January 1977 have been covered.