A formula for half-life of proton radioactivity

We present a formula for proton radioactivity half-lives of spherical proton emitters with the inclusion of the spectroscopic factor. The coefficients in the formula are calibrated with the available experimental data. As an input to calculate the half-life, the spectroscopic factor that characterizes the important information on nuclear structure should be obtained with a nuclear many-body approach. This formula is found to work quite well, and in better agreement with experimental measurements than other theoretical models. Therefore, it can be used as a powerful tool in the investigation of proton emission, in particular for experimentalists.     

Study of gamma ray energy absorption and exposure buildup factors for ferrites by geometric progression fitting method

The gamma ray energy absorption and exposure buildup factors (EABF and EBF) were calculated for ferrites such as cobalt ferrite (CoFe₂O₄), zinc ferrite (ZnFe₂O₄), nickel ferrite (NiFe₂O₄) and magnesium ferrite (MgFe₂O₄) using five parametric geometric progression (G-P fitting) formula in the energy range 0.015–15.00?MeV up to the penetration depth 40 mean free path (mfp). The obtained data of absorption and exposure buildup factors have been studied as a function of incident photon energy and penetration depth. The obtained EABF and EBF data are useful for radiation dosimetry and radiation therapy.     

Investigation of some nuclear engineering materials in terms of gamma ray buildup factors at experimental energies used in nuclear physics experiments

ABSTRACT

In shielding studies, the gamma ray buildup factor is referred to an attenuation correction when the narrow beam transmission geometry conditions are not met. This is the case if there is a beam divergence and a considerably thick material is used as shield. In the present work, a linear logarithmic interpolation based on five parameter geometric progression (G-P) fitting method was used to calculate energy absorption (EABF) and exposure buildup factors (EBF) at discrete energies for some standard nuclear engineering materials (SNEM) such as concrete, Pb glass, brass, bronze and stainless steel, and for some recently developed shielding alloys and glasses. Calculations were made at different penetration depths (1–20?mfp) using photons emitted from the standard radioactive sources such as ¹³³Ba (0.356 MeV), ¹³⁷Cs (0.662 MeV), ⁶⁰Co (1.173, 1.332 MeV) and ²²Na (0.511, 1.275 MeV). Results have been compared with MCNP6.1 Monte Carlo simulation code wherever possible and a reasonable agreement (Relative difference around 10% up to 10?mfp except for Pb glass) has been achieved. Results also showed that the gamma ray buildup correction is necessarily required since buildup factors are greater than unity even at lowest penetration depth, i.e. 1?mfp. The reported data on EABF and EBF for the energy values of radioactive sources may be of practical use in shielding calculations and estimations.     

α Decay Properties of Even-Even Nuclei~(296-308)120 Within the Two-Potential Approach

In the present work,we predict the α decay half-lives of unknown even-even nuclei ~(296-308)120 within the two-potential approach,whose α decay energy Qa is calculated using WS3+mass model.To reduce the deviations between the predictions and experimental data due to nuclear shell effect,the analytic formula of α decay hindrance factor is introduced to the two-potential approach,whose parameters had been extracted from even-even nuclei in the region of 82 Z 126 and 152 N 184 in our previous work [Deng et al.,Chin.Phys.C 42(2018) 044102].In addition,for comparing,we use a type of α decay general formula Universal Decay Law(UDL) and a semi-empirical formula in the superheavy nucleus(SEMFLS) to calculate the half-lives of even-even nuclei ~(296-308)120.The results indicate that our predicted values and the calculated values of the above two empirical formulas are mutually confirmed.Meanwhile,we systematically study α decay chains of ~(296-308)120 and predict the decay modes for superheavy nuclei to help to identify new superheavy isotopes.     

基于Weizsäcker-Skyrme核质量公式研究原子核基态性质

基于一个半经验的原子核宏观 微观质量公式——Weizsäcker-Skyrme质量公式, 研究了原子核的形变、 滴线、 壳能隙和超重核α衰变能等相关性质, 发现该模型能较好地再现实验结果。与此同时, 探索了原子核对称能系数对原子核质量公式的影响和超重稳定岛的可能位置。     

Gamma Dose Distribution Studies in Ducted Shield Material Having Different Configurations

In the present work the radial distribution of total gamma doses arising from the interaction of reactor neutrons and gamma radiations inside ilmenite heavy concrete shield are measured. The ilmenite concrete is pierced with neutral beam injector ducts having different diameters and lengths. The results obtained show a relative increase in radial gamma doses at a distance of 10 cm from the neutral beam end. An empirical formula was obtained, fitting the measured gamma doses at the peak position in good agreement within a factor of 1.27. Moreover the variation of the total gamma radiation was measured along straight filled ducted with different diameters and length. The experimental data obtained show a reasonable agreement with calculated ones. The scattered as well as unscattered components of the gamma radiation transmitted through a straight duct were investigated. An empirical formula describing this behaviour was obtained.     

Developing a mailed phantom to implement a local QA program in Egypt radiotherapy centers

In this work, a simple method that differs from the IAEA/WHO Thermoluminescent dosimeters (TLD) postal quality assurance (QA) program is developed. A small perspex; polymethyl methacrylate (PMMA), phantom measured 50?mm?×?50?mm?×?50?mm is constructed to be used for absorbed dose verification of high-energy photon beams in some major radiotherapy centers in Egypt. The phantom weighted only 140.7?g with two buildup covers weighted 14.8 and 43.19?g for the Cobalt-60 and the 6-MV X-ray beams, respectively. This phantom is aimed for use in the future’s external audit/QA services in Egypt for the first time. TLD-700 chips are used for testing and investigating a convenient and national dosimetry QA program. Although the used methodology is comparable to previously introduced but new system; it has smaller size, less weight, and different more available material. Comparison with the previous similar designs is introduced. Theoretical calculations were done by the commercial Eclipse treatment planning system, implementing the pencil beam convolution algorithm to verify the accuracy of the experimental calculation of the dose conversion factor of water to the perspex phantom. The new constructed small phantom and methodology was applied in 10 participating radiotherapy centers. The absorbed dose was verified under the reference conditions for both ⁶⁰Co and 6-MV high-energy photon beams. The checked beams were within the 5% limit except for four photon beams. There was an agreement of 0.2% between our experimental data and those previously published confirming the validity of the applied method in verifying radiotherapy absorbed dose.     

短圆管换能器辐射阻抗

辐射阻抗是换能器最重要的辐射声场特性参数之一,影响着换能器的谐振频率、频带宽度、效率以及辐射声功率等.随着圆管换能器半径和高度的不断变化,想直接得到声场瑞利积分的解析解是十分困难的.该文通过建立经验公式模型来解决此问题.首先,通过有限元软件计算圆管换能器辐射阻抗的数值解.然后利用MATLAB工具进行曲线拟合.经过反复逼...     

Particle-hole excitations in nucleus-nucleus collisions

Nucleus-nucleus collisions lead to nuclear excitations which can be expressed in terms of particles and holes. An empirical formula is presented to calculate this initially degree of freedom. The formula is tested against data and found to have a large range of validity with respect to projectile masses and bombarding energies.     

Gamma and enclosure dosimetry for TL/ESR dating with the new Al2O3: C TL dosemeter

Al₂O₃: C manufactured by LAIKS-CORUND, Ekaterinenburg, Russia, offers several advantages for the measurement of environmental radiation: stability, low self-dose, high sensitivity and energy deposition features under gamma and beta irradiation very similar to quartz and quartz-like TL minerals. In the present work those properties were tested for in situ gamma dosimetry, by comparison with other dosimetric techniques. It was confirmed that this phosphor is very well adapted to this purpose. On the other hand, the new alumina can be made insensitive to external alpha radiation by means of thermal treatments. This α-insensitized alumina is very interesting for enclosure dosimetry in the perspective of quartz inclusion dating. In this technique, the quartz grains to be dated are faithfully simulated by alumina: the phosphor allows us to measure directly the dose that would be experienced by quartz grains (HF etched, as usual). However, because the attenuation of beta radiation by coarse grains must be taken into account in inclusion dating, the role of this factor was theoretically and experimentally—with Al₂O₃—explored. The preliminary experiments indicated that enclosure dosimetry with this new alumina was a promising technique.     

Three dimensional (Z‐dependence), collective and individual semi‐empirical formulae for L X‐ray production and ionization cross section by protons impact within corrected ECPSSR theory and updated experimental data: a review

In this paper we propose a new three dimensional semi‐empirical formulae for the deduction of L X‐ray production and ionization cross sections by introducing the dependence on the atomic number of the target, noted as ‘Z‐dependence’. The data are also fitted collectively and separately (for each element) by analytical functions to calculate semi‐empirical cross sections. For this purpose, the corrected ECPSSR model (noted as eCPSSR) and the published experimental data of L_α, L_β and L_γ X‐ray production and L₁, L₂ and L₃ ionization cross sections in the period (1950–2014) are combined to calculate the semi‐empirical ones for a wide range of elements by proton impact. The semi‐empirical cross sections (for the three x‐rays lines L_α, L_β, L_γ and the three sub‐shells L₁, L₂, L₃) are then deduced by fitting the available experimental data normalized to their corresponding theoretical values (using the eCPSSR model) giving a better representation of the experimental data for the individual interpolation. At last, a comparison is made between the three semi‐empirical formulae reported in this work. Copyright © 2016 John Wiley & Sons, Ltd.     

Effect of Nuclear Binding Energy to K Factor

We modify the square of virtual photon four-momentum by using nuclear binding energy formula, and calculate the effect of nuclear binding energy to K factor and Compton subprocess and annihilate subprocess in A-A collision Drell-Yan process. The outcome indicates that the effect of nuclear binding energy to K factor is obvious in little x region and it would disappear gradually as x increases.     

核爆炸光辐射探测中的大气传输性能研究

从核爆炸光辐射特点出发, 结合我国中纬度地区大气特点,研究了(0.2～1.2)μm波段大气传输性能。通过实际测量数据分析可知,大气对（0.2～1.2)μm光辐射起主要作用的成分有水蒸气、二氧化碳和臭氧的分子吸收和散射以及气溶胶大粒子的散射。综合考虑这些因素,改进了水平路径传输上（0.2～1.2）μm光辐射大气传输经验方程。计算机仿真结果表明：该方程能体现我国中纬度地区光辐射的传输情况,对（0.4～0.8）μm可见光波段能很好地吻合。将（0.4～0.8）μm波段光辐射大气传输定量计算结果直接应用到基于可见光辐射探测的核爆炸探测子系统中,模拟核爆炸探测,实验结果表明：与传统大气传输计算软件的定性结果相比,该方法的测量精度有明显的提高。     

关于原子核电荷半径的研究

结合原子核电荷半径实验数据, 对885个中子数N≥8和质子数Z≥8的核电荷半径做了系统的研究. 对于单参数核电荷半径公式, Z^1/3律公式计算的结果优于A^1/3律的结果, 而对于两参数和三参数公式, Z^1/3律和A^1/3律的结果基本相当. 考虑到壳效应及奇偶摆动现象, 在原有的三参数公式基础上提出了加入Casten因子项和δ项的核电荷半径新公式. 利用该公式计算得到的核电荷半径理论值和实验值符合得非常好, 均方根偏差仅为σ=0.0266 fm, 此值比常用的三参数公式的结果下降了近50%, 理论计算值能更好地反映出壳效应及核电荷半径奇偶摆动的变化趋势.     

Simulation of the radiation fields from ionizing radiation sources inside the containment in an accident

In the present work, a set of codes used for simulations of the radiation fields from ionizing radiation sources inside the containment in an accident is described. A method of evaluating the gamma dose rate from a space and energy distributed source is given. The dose rate is calculated by means of the design point kernel method and using buildup factors. The code MCU-REA with the ORIMCU module is used for the burnup calculations.     

Superheated emulsions and track etch detectors for photoneutron measurements

This paper describes the criteria behind the selection of neutron detection techniques for photoneutron dosimetry as well as the methods adopted to obtain dosimetric readouts. The work was conducted within the framework of Working Group 9 (WG9 Radiation Protection Dosimetry in Medicine), coordinated by the European Radiation Dosimetry Group (EURADOS). WG9 research aims at estimating the risk of second cancer induction due to radiation therapy. Therefore, a comprehensive experimental programme was devised to measure doses received by non-target organs-at-risk (OAR) during radiation therapy. The techniques described in this work were selected and used for the neutron dosimetric assessment during in-phantom simulations of clinical prostate radiotherapy treatments, carried out in three European facilities. Non-conformal standard fields were used as a common reference between different facilities.Performing neutron measurements near linacs is a complex task, because of the intense pulsed photon primary field. Therefore, photon insensitive dosimeters such as superheated emulsions (SE) and solid state nuclear track detectors (SSNTD) were chosen. Their readout procedures were carefully assessed. Methods were developed to count the large number of tracks and bubbles in SE. These are described in detail in the present work, along with a brief introduction to the detector physics.     

MBBA和CC混合物的螺距测量及螺距与温度关系经验公式

我们用布喇格散射法测定了混合液晶MBBA:CC=22.7:77.3(重量比)在不同温度下的螺距。从测得的结果,结合文献中对其它材料所测的数据,我们提出一个螺距p随温度T变化的经验公式:p=p₀-b/(T-T₀)对左旋材料螺距p<0,对右旋材料p>0。除接近相变温度或旋向翻转温度附近外,公式不但适用于单体螺旋状液晶也适用于混合液晶。对一些材料,从实验数据中定出了与它们相对应的常数p₀,b和T₀。 关键词：     

Experimental Procedures for Sensitive and Reproducible In Situ EPR Tooth Dosimetry

In vivo electron paramagnetic resonance (EPR) tooth dosimetry provides a means for non-invasive retrospective assessment of personal radiation exposure. While there is a clear need for such capabilities following radiation accidents, the most pressing need for the development of this technology is the heightened likelihood of terrorist events or nuclear conflicts. This technique will enable such measurements to be made at the site of an incident, while the subject is present, to assist emergency personnel as they perform triage for the affected population. At Dartmouth Medical School this development is currently being tested with normal volunteers with irradiated teeth placed in their mouths and with patients who have undergone radiation therapy. Here we describe progress in practical procedures to provide accurate and reproducible in vivo dose estimates.     

Radiation dose reconstruction and nuclear-explosion dating in the East-Kazakhstan region

The radioecological situation in the East-Kazakhstan region was studied by electron paramagnetic resonance (EPR), radiography and nuclear spectroscopy methods. The eastern part of this region borders the Semipalatinsk nuclear test site. Radiation doses for 33 residents of this region were measured by EPR dosimetry in tooth enamel. It was found that for 25% of the residents the measured radiation doses do not exceed the background level. The rest of the doses exceed the background level by a factor of 2–4 on the average. A new method of nuclear explosion dating was developed on the basis of the EPR measurements of the free radical concentration in annual tree rings. Their maximal concentration corresponds to the years when nuclear explosions were executed. The obtained results correlate well with the commonly accepted radiography method. Both methods show a maximum of radionuclide levels in the years of nuclear testing. The plutonium-239 content in residents hair samples was found to be equal to (0.8±0.2)·10^?9 g/kg and with activity of 1.9±0.4 Bq/kg. This is by a factor of 20 higher than the permitted content for the population.     

Effective medium theory of checkboard structures in the long-wavelength limit

Effective medium theory is a powerful tool to solve various problems for achieving multifarious functionalities and applications. In this article, we present a concise empirical formula about effective permittivity of checkboard structures for different directions. To verify our empirical formula, we perform simulations of checkboard periodic structures in squares, rectangles, and sectors in two dimensions. Our results show that the formula is valid in a large range of parameters. This work provides a new way to understand and design composite materials, which might lead to further optical applications in transformation optics.