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Experimental data for monitoring microcrack nucleation and propagation in metallic samples are obtained for copper. New experimental results from a study performed with a transmission electron microscope of crack nucleation in copper samples deformed by stretching are presented. The results of monitoring a dislocation-free fracture zone in front of a microcrack tip are described. It is found experimentally that the metal in this zone underwent a transition from a crystalline into an amorphous state and embryonic microcracks originated precisely in this zone. Translated from Atomnaya énergiya, Vol. 106, No. 2, pp. 88–93, February, 2009.  相似文献   

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The state of mineral reserves of thorium-bearing raw materials from the Kola Peninsula and other regions of Russia and the Commonwealth of Independent States is examined. Schemes for secondary extraction of thorium during processing of the most accessible raw-material sources – loparite, baddeleyite, monazite, pyrochlore, and columbite-tantalites – are presented. In theory, ores of operating mines, thorium-bearing wastes obtained during decontamination of reprocessed concentrates, as well as raw materials sources best prepared for processing, for example, perovskite concentrate from the Afrikanda field, rare-metal raw material from the Tomtor field, baddeleyite concentrate, and others, can meet the demand. It is concluded that in the near future about 300 tons thorium/yr can be obtained from accumulated wastes of operating mines and as a by-product of processing rare-earth raw material.  相似文献   

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A strategy for environmental safety of radiologically dangerous objects is examined for one such object. The steps in performing the work oriented toward environmental safety are shown. The most likely variants for handling radioactive wastes are presented. The technological operations performed to ensure environmental safety of the object are examined. The choice of the final variant for increasing environmental safety is made after economic and environmental evaluation. The strategy developed for ensuring environmental safety can be used to examine other radiologically dangerous objects.  相似文献   

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Results of environmental radioactivity monitoring around Qinshan Nuclear Power Plant (QNPP) are reported in this paper. From 1992 to 2005, concentrations of 90Sr, 137Cs and 3H in terrestrial freshwater are (4.4±1.7) mBq·L-1, (0.3±0.1) mBq·L-1 and (1.6±0.5) Bq·L-1, respectively, and (2.8±2.4) Bq·L-1 of 3H in rainwater. Concentrations of 90Sr, 137Cs and 3H in the seawater samples collected from sea area nearby QNPP are (5.4±4.1) mBq·L-1,(0.7±0.2) mBq·L-1 and (1.0±0.5) Bq·L-1, respectively. Concentrations of 90Sr, 137Cs and 3H in the total waste water discharged from NPP-I are (4.0±1.8) m Bq·L-1, (1.0±0.5) mBq·L-1 and (2.8±2.2) Bq·L-1, respectively, and (1.4±0.4)Bq·L-1 of 3H in seawater sampled from No.1 outlet. Atomspheric 3H concentration in 1993 ~ 2005 at two monitoring sites is (78.9±96.3) and (64.2±40.2) mBq·m-3, respectively, with an increasing trend after 2003. Atmospheric 14C concentrations at the two sites are in the same levels as the background and data of the reference site.  相似文献   

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The main drawback of the existing normative base of the systems used for accounting for, monitoring, and physical protection of radioactive substances and wastes is that these systems ignore the experience which has been accumulated for nuclear materials. It is proposed in the present paper that the program-technological complexes used in the accounting and monitoring systems be unified and that the successful experience in developing such complexes at the Russian Science Center Kurchatov Institute in the form of the KI-MAKS system, which makes it possible to solve the problems of automatically accounting for, monitoring, and reporting on nuclear materials and radioactive substances and wastes, be utilized. It is shown that an effective solution of the problems of accounting for, monitoring, and physical protection in terms of cost-effectiveness can be attained by using the existing program-technological complex called a probabilistic expert-consulting system, which makes it possible to perform a quantitative analysis of the level of the safety culture in the nuclear fuel cycle. __________ Translated from Atomnaya énergiya, Vol. 101, No. 3, pp. 208–214, September, 2006.  相似文献   

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The study and conservation of museum collections calls for the application of scientific methodology in the examination, analysis and dating of objects. Because the nature of these objects makes sampling undesirable, and often even impossible, museum laboratories continuously look out for new nondestructive techniques, which can be adapted for their use. Chemical analysis of museum objects, including trace element analysis, can provide information regarding provenance as well as the technology employed in the preparation of the materials and the manufacture of the objects. A very sensitive and precise analysis may thus provide a chemical “fingerprint” of an object, a school or a cultural group. On the other hand, detailed and precise chemical analysis can also provide insight into the processes involved in the deterioration of the materials of museum objects. Analytical requirements for the various types of materials, of interest in museum research are reviewed along with the classical analytical techniques widely used in museum research.  相似文献   

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环境本底辐射监测系统及其监测结果分析   总被引:1,自引:0,他引:1  
本文介绍了中国科学院近代物理研究所为监测所区中子和γ本底而设置的四个环境站的分布及监测方法,提供了对所区周围天然本底监测的典型数据及图表,分析了600kV高压倍加器运行时环境站数据的相应变化,最后就各站所测的结果与国内外有关数据作了对比。  相似文献   

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李洋  康晶  王彦  顾志杰 《辐射防护》2021,41(Z1):12-14
为了全国核基地与核设施辐射环境现状调查与评价科研专项中辐射环境现状评价工作的开展,项目组建立了一种基于环境监测数据的辐射环境现状评价方法。本文对该方法进行了介绍,对实施过程中遇到的问题及实施效果进行了分析,并提出了改进的建议。  相似文献   

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Translated from Atomnaya Énergia, Vol. 67, No. 5, pp. 347–351, November, 1989.  相似文献   

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夏益华  王绍林 《辐射防护》2017,37(4):327-336
辐射环境监测中的“取样环节”,常常可以成为监测结果总变异性的重要来源,但“如何进行代表性取样”、“如何设计合理的取样方案”,却是目前普遍没有受到应有重视的问题。本文在介绍国际辐射单位与测量委员会(IRCU)75号报告部分相关内容的基础上,结合我国目前的实际情况对环境取样的代表性和某些相关问题进行了讨论。旨在抛砖引玉,引起大家对环境取样代表性问题的重视,从而推动这方面工作的改进。  相似文献   

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Under discussion is the management of long-lived high-level wastes in the nuclear energy sector of Russia, the development of which on a large scale in the next century is motivated by the need for arresting the increasing consumption of fossil fuels. The prerequisites for the nuclear power growth consists in the design of naturally safe reactors and development of a transmutational nuclear fuel cycle (NFC) technology. The choice of operations in such a cycle and of their quantitative characteristics, is aimed at minimizing the wastes to approach the radiation balance with the natural uranium extracted and put to use. The paper discusses the way the approximation to the balance between the raw material and waste activity is influenced by introduction of the transmutational NFC (in case 2), inclusion of transmutation reactors into the energy mix (case 1), partial disposal of actinide wastes into outer space, and by recycling of protactinium (case 3). It is shown that such a balance can be sustained for a considerable time in cases 2 and 3 or throughout the operation stage of the future nuclear power (case 1).  相似文献   

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