RBS and XFA analysis of polyimide films from the Mir space station

The elemental composition of polyimide film contamination was studied by the RBS and XFA methods. The films were exposed to the space environment aboard the Mir orbital space station during the KOMPLAST in-flight experiment. It was shown that the prevalent deposit element was silicon, which agrees with measurements performed on other spacecrafts.     

Radioactive contamination of the atmosphere of Cairo,Egypt, from the Fukushima Dai-ichi nuclear plant accident

Radioactive contamination in air dust particles of Cairo atmosphere from the Fukushima accident was detected by the gamma-ray spectroscopy technique. Analysis of the spectra obtained by using an High-Purity Germanium detector showed that there were some traces of ¹³¹I and ^{134, 137}Cs. Estimate and study of concentration of those radionuclides were done over a period of about 5 months after the accident. Comparison with corresponding results in different countries all over the world has been performed.     

Application of SSNTDs to investigations of radiation accident after-effects

Track methods and devices used for studies conducted after radiation accidents are considered. Solid State Nuclear Track Detectors (SSNTDs) are applied for measurements of contamination in soil, water, biological and other objects of alpha-emitting radionuclides, as well as for estimation of neutron doses by means accident dosimeters. Known radiation accidents (Chernobyl a.o.) and potential emergencies (sunken submarine “Komsomolets”, nuclear reactors) are discussed. Some result of SSNTD application at after-accident period are presented.     

Influence of contamination layer on thickness evaluation by X-ray reflectometry

In this study, the effect of allowing for a contamination layer on a SiO₂ film/Si substrate system on thickness determination by X-ray reflectometry (XRR) was investigated. The calculated XRR profiles obtained using a calculation model that utilizes a contamination layer for analysis showed good agreement with measured profiles. Further, the obtained physical structures were promising and within acceptable limits. Where the existence of a contamination layer was ignored in the calculation process, a part of the thickness of the contamination layer was incorporated into the determined thickness of the SiO₂ layer. In that case, the evaluated thickness was proportional to the density ratio between the contaminated and SiO₂ layers. The results of investigation of the effect of X-ray energy on layer thickness determination indicated that the effects of contamination also depend on the X-ray energy used for XRR measurements. These effects increase in the case of experiments that employ X-ray energy with a high contrast for the contamination.     

Franco-Russian comparison of mixed neutron and gamma radiation field dosimeters at the Silène reactor

This paper gives the results of dosimetry measurements carried out in the Silène reactor at Valduc (France) with neutron and photon dosimeters in mixed neutron and gamma radiation fields, in the frame of a Franco-Russian comparison of dosimeters. Neutron dosimetry was supplied by passive semiconductors, activation detectors and nuclear track detectors. For photon dosimetry, thermoluminescent and passive semiconductor detectors were used. The experiments were located at 3 m from the reactor core, in free air and also at the front and back of a tissue-equivalent phantom. The pulse operating mode of the reactor was used to simulate a criticality accident with solid fissile material, while the free evolution mode simulated a criticality accident in a fissile solution. The photon absorbed dose showed a slight increase on entering the phantom compared to measurements in free air, probably due to backscattering by the phantom. At the rear of the phantom, the neutron kerma was four times lower than on the front, whereas the photon dose was only two times lower. The heterogeneity of dose inside the phantom was far greater for neutrons than for photons.     

Creating a baseline radiological standard for the waste isolation pilot plant underground

The Waste Isolation Pilot Plant (WIPP) is a deep underground geological repository for defense transuranic wastes. The creation of a full baseline radiological standard for the WIPP underground is essential in order to evaluate and account for the influence of the naturally occurring radioactive materials, and to prepare for any suspected contamination or the very unlikely event of a real accident scenario. In this report, we describe the establishment of the baseline information using the gamma background dose rate measurements and the salt rib smears of surface removable alpha and beta activities throughout the WIPP underground. The average background gamma dose rate in the WIPP underground is 8.27 x 10(-9) +/- 1.65 x 10(-9) Gy/h while the gamma dose rate on the WIPP surface is 3.46 x 10(-8) +/- 1.65 x 10(-9) Gy/h. The overall surface average alpha activity in the underground is 8.52 x 10(-5) +/- 1.22 x 10(-4) Bq/cm2 (at 1sigma level) with the minimum detectable activity (MDA) of 4.81 x 10(-4) Bq/cm2. The overall surface average beta activity is 8.25 x 10(-4) +/- 8.17 x 10(-4) Bq/cm2 (at 1sigma level) with the MDA of 3.19 x 10(-3) Bq/cm2. This baseline standard will be beneficial to the overall WIPP operational facility, ensuring the worker safety and adding to public confidence in the operation of the WIPP.     

同步辐射X射线干涉的实验研究

介绍在北京同步辐射装置上进行的国内首次LLL型X射线干涉实验研究,在X光底片上观察到了Moire干涉条纹,为进一步利用X射线干涉技术实现纳米测量打下了初步基础.     

An environmental BeO-OSL dosimeter for emergency response

A conceptual design is presented to use measurements of localized absorbed dose in inner cities for production of high resolution maps of the radioactive contamination following a nuclear emergency or radiological attack. The doses are derived from luminescent detectors pre-fixed at places of high importance (e.g. public squares). For such an environmental dosimeter, BeO is used, which can be read out using optically stimulated luminescence (OSL). A suitable casing of black Perspex has been developed to give a sufficiently accurate estimate of the air kerma value at the detector position. The dosimeter is characterized according to light tightness, dose response and angular photon energy dependence. A short overview of the approach for map production is also given.     

铅基反应堆自然循环与应急余热排出研究

自然循环特性是铅基反应堆一回路的关键运行特性,对反应堆的非能动应急余热排出具有重要的影响,自然循环特性与余热排出能力是反应堆热工水力研究的重要内容。采用多孔介质方法,建立了CiADS铅基堆1/4三维计算模型,使用FLUENT程序对额定工况与低功率工况进行稳态计算。为了研究全厂断电事故下的余热排出过程,从热工水力的等效原则出发,尝试建立二维等效模型以提高瞬态计算效率。结果表明,CiADS铅基堆具备低功率自然循环运行能力和一定的事故容错能力;二维等效模型与三维模型计算结果吻合较好,可用于瞬态下的简化分析;CiADS铅基堆的非能动余热排出系统能够较好地应对全厂断电事故,反应堆具有良好的固有安全性。     

微型数据采集器及其在加速器周围辐射场实时监测中的应用

各种类型加速器周围的辐射场变化是很复杂的, 只有对其进行连续的实时监测才能准确地掌握全面资料. 以往的数据采集系统用的是模拟信号长距离传输方式, 采集器体积较大, 存储技术上也显落后, 已不能适应当今的需求. 为辐射场实时监测研制的微型数据采集器采用了先进的设计理念, 具有体积小、通讯能力强、数据存储量大且断电数据不丢失的特点, 可运行于局域网环境. 它既可利用局域网远距离向控制计算机传递数据, 也可用便携式PC通过串口就近读取数据. 所以它不但适于固定场所的连续监测, 也可灵活地用于临时测量场所. 介绍了它的主要性能和在各类型加速器周围所做测量的结果.     

应用于ICF实验的软X射线平面镜反射率

在北京同步辐射装置上,通过对应用于惯性约束聚变（ICF）实验的平面镜反射率的进一步研究,提高了辐射温度的测量精度。进行了对软X射线平面镜反射率的测量、反射镜的清洗、反射率的模拟计算,证明影响反射率变化的主要因素是平面镜的安装角度和沾污。实验结果表明:平面镜的沾污主要来源于ICF实验中的油沾污,采用射频辉光放电清洗非常有效。     

Mössbauer Study of Iron-Containing Atmospheric Aerosol Collected During the Chernobyl Accident

During the Chernobyl accident a large quantity of radionuclides was released into the troposphere and contaminated a wide geographical area. The present study concentrates on atmospheric iron. The Mössbauer measurements were performed on the atmospheric aerosol collected during the accident on 27–30 April 1986 in Warsaw and in Legnica, Poland. Results were compared with the data obtained for samples collected at the same sites just before the accident. The observed increase in iron concentration determined by Mössbauer effect could be explained by the enrichment of natural iron in ⁵⁷Fe isotope in ⁵⁶Fe(n,)⁵⁷Fe reaction.     

Numerical procedures and their practical application in PV modules analyses. Part I: air mass

The subject of the article is aspects of PV modules and cells measurement, with the use of natural sunlight. A light source is an important element during calibration and measurements of solar cells and modules. All designers of artificial light sources try to recreate natural light using so called measurement tables. The correctly performed measurement, i.e. meeting all the appropriate atmospheric conditions, guarantees obtaining the result with the use of a reference spectrum. The article has two main aims. The first aim of the article is to answer the question asked earlier - if the sunlight spectrum registered in appropriate conditions is so good that it serves as the reference spectrum - then, in practice, during measurements carried out with its use, certain problems occur regarding the correct measurement results or their interpretation. The second aim regards presenting detailed numeric procedures in order to enable readers to associate air mass with geographical coordinates and Local Solar Time of their study/laboratory location. Moreover, having the data from their local meteorological station, they will be able to estimate the occurrence of the measurement spectral error of the tested cell/module not only from the group referred to in the article but also for others, for which they have a dedicated characteristics of spectral response.     

A thermoluminescence study of mineral silicates extracted from herbs in the dose range 0.5–5 Gy

The presence of silicates in many personal objects suggests their potential use at low dose as fortuitous dosimeter in an accidental radiological exposure, when conventional dosimetry is not available. The goal of the present work is the dosimetric characterization of mineral silicates extracted from the plant Hibiscus Sabdariffa L, known as Jamaica flower, in the dose range 0.5–5 Gy. By studying the radiation-induced signal in time, the temperature integration region between 210 °C and 250 °C was found to be the most stable and also reduced the effects of thermal fading in the dose reconstruction process; the dose response curve was linear between 0.5 Gy and 5 Gy. By checking the change in sensitivity after repeated exposures to ionizing radiations and to high temperature heating, no variation in the glow curve shape or peak intensities were detected. To eliminate a pre-existing background signal, all the characterization measurements were performed with aliquots “annealed” by a preliminary readout of the TL.     

利用声辐射模态重构任意目标的散射声场

水下目标散射声场的重构可以作为水下目标散射特性的研究基础。本文主要利用声辐射模态对水下目标进行散射声场重构研究。首先,在借助声传递矩阵给出的任意结构声辐射模态的流体域求解方法基础上,通过理论证明了目标的散射声压与声辐射模态具有函数关系。其次,借助声场分布模态的概念,同时考虑到声场分布模态病态及声压测量易受噪声污染,提出基于声辐射模态的正则化散射声场重构算法。仿真结果表明,波数越低,重构所需声辐射模态阶数越少,在较高波数时仅需总模态数的大约20%即可对声场进行重构。与基于边界元的声场重构算法相比,计算量减小了至少80%,且克服了赫姆霍兹积分方程最小二乘法仅对球壳结构的重构效果较好而不适用于长条形结构重构的缺陷。     

Radon survey and soil gamma doses in primary schools of Batman,Turkey

A survey was conducted to evaluate levels of indoor radon and gamma doses in 42 primary schools located in Batman, southeastern Anatolia, Turkey. Indoor radon measurements were carried out using CR-39 solid-state nuclear track detector-based radon dosimeters. The overall mean annual ²²²Rn activity in the surveyed area was found to be 49 Bq m^?3 (equivalent to an annual effective dose of 0.25 mSv). However, in one of the districts (Besiri) the maximum radon value turned out to be 307 Bq m^?3. The estimated annual effective doses are less than the recommended action level (3–10 mSv). It is found that the radon concentration decreases with increasing floor number. The concentrations of natural and artificial radioisotopes were determined using gamma-ray spectroscopy for soil samples collected in close vicinity of the studied schools. The mean gamma activity concentrations in the soil samples were 31, 25, 329 and 12 Bq kg^?1 for ²²⁶Ra, ²³²Th, ⁴⁰K and ¹³⁷Cs, respectively. The radiological parameters such as the absorbed dose rate in air and the annual effective dose equivalent were calculated. These radiological parameters were evaluated and compared with the internationally recommended values.     

北京同步辐射装置X射线衍射实验站在材料科学研究中的应用

简述了北京同步辐射装置X射线衍射实验站的实验装置,工作性能.利用X射线衍射仪开展了非晶周期多层膜、半导体超晶格结构研究,测量了Si₃N₄材料残存应力微区分布.     

Tagungsberichte

Like in other European countries, due to the accident at the Chernobyl nuclear power plant in 1986 the radioactive contamination level of the biological chain increased significantly in Hungary. The external and internal dose burden had a low-dose effect on plants ranging within the dose internal of stimulation and thus exhibiting a biopositive influence on the physiological functions.

Nach dent Unfall im Kernkraftwerk Tschernobyl im Jahre 19S6 slieg in Ungarn die radioaktive Kontamination der biologischen Kette erheblich an. Die externe und interne Strahlenbelastung hatte eine niedrigc Dosiswirkung auf Pflanzen, bewegte sich inncrhalb der Dosisspanne der Stimulation und wies somit einen biopositiven Einfluβ auf die physiologischen Funkionen auf.     

Polymer electrolyte fuel cell performance degradation at different synchrotron beam intensities

The degradation of cell performance of polymer electrolyte fuel cells under monochromatic X‐ray irradiation at 13.5 keV was studied in galvanostatic and potentiostatic operation modes in a through‐plane imaging direction over a range of two orders of magnitude beam intensity at the TOMCAT beamline of the Swiss Light Source. The performance degradation was found to be a function of X‐ray dose and independent of beam intensity, whereas the degradation rate correlates with beam intensity. The cell performance was more sensitive to X‐ray irradiation at higher temperature and gas feed humidity. High‐frequency resistance measurements and the analysis of product water allow conclusions to be drawn on the dominating degradation processes, namely change of hydrophobicity of the electrode and sulfate contamination of the electrocatalyst.