Investigation of radioactive contamination of graphite samples from the AM reactor

The world’s first nuclear power plant operated for almost 48 years. Over this period of time, the neutron fluence on the graphite masonry reached ∼10²² cm⁻², which resulted in activation of the impurities present in the graphite. During operation, incidents occurred with loss of seal and sometimes loss of integrity of the fuel-element claddings in some cells and particles of the fuel and steam-water mixture entered the graphite masonry. This resulted in radiation contamination with a complex radionuclide composition. Experimental information about the content and distribution of radionuclides in the spent nuclear graphite is needed in order to plan methods and periods of time for disassembly and salvaging of the graphite masonry of the stopped reactor taking account of the dose loads on the workers and the ecological safety norms. The problems which can be solved on the basis of the present work included the determination of the ¹⁴C and ³H contents by liquid-scintillation β spectrometry, analysis of the actinide content by direct γ spectrometry, and neutron-activation analysis followed by γ spectrometry. These investigation yielded new data on the content of fission products and activation impurities in graphite. __________ Translated from Atomnaya énergiya, Vol. 101, No. 5, pp. 358–364, November, 2006.     

Metadata on the radioactive contamination of environmental objects on the territories of Russia and the USSR

A unique data archive, accumulated at the Taifun Scientific and Industrial Association in 1954–2005, on the radioactive contamination of the environment on the territory of the USSR and Russia is presented. The archive contains data on the yearly total β activity of atmospheric fallout on the underlying surface, the total volume β activity in the atmosphere at the ground, the results of measurements of the ⁹⁰Sr and ¹³⁷Cs content in samples combined over one month or quarter, atmospheric aerosols and fallout on individual points, the volume activity of tritium and ⁹⁰Sr in water, rivers, lakes and seas, and the radionuclide contamination density of the territories of populated points as a result of the Chernobyl accident. __________ Translated from Atomnaya énergiya, Vol. 101, No. 2, pp. 149–152, August, 2006.     

Analysis of the radioactive contamination of the environment due to decommissioned objects of the nuclear-powered fleet in northwestern Russia

The risk of radioactive contamination of the environment is assessed using a comprehensive approach and examination of the questions, including analysis of the structure of the objects and the interaction between them, determination of the sources of the real and potential danger, development of scenarios for accidents and assessment of their probability, the radiation consequences of exposure of workers, the general public, and the environment during salvaging of the nuclear-powered fleet in the Russian northwest. A systematization of the risk is made and the distribution according to the degree of danger is determined. __________ Translated from Atomnaya énergiya, Vol. 101, No. 1, pp. 23–34, July, 2006.     

Probability of detection of local radioactive contamination

Translated from Atomnaya Énergiya, Vol. 68, No. 5, pp. 378–381, May, 1990.     

Remediation of zones of local radioactive contamination

A methodology remediating zones of local radioactive contamination is presented. It is based on a classification of the zones taking account of the contribution of external and internal irradiation to the total dose load to the public. The criteria for identifying such loads and the steps required for their remediation are identified. A radiation-ecological validation of the decrease in the external irradiation dose to the public in zones of local radioactive contamination is given. __________ Translated from Atomnaya énergiya, Vol. 100, No. 2, pp. 125–134, February, 2006.     

稀土矿中的天然放射性核素^138La和^176Lu

用高纯锗γ谱仪对一些稀土矿中的~(138)La和~(176)Lu含量进行了测量。发现在一个稀土矿中存在着丰富的~(138)La和~(176)Lu,而且它们的含量相差很大,它们在矿中的存在也并不表现正相关性。同时发现在这个稀土矿中~(40)K的含量特别低,这可能对辐射防护和研究稀土矿的形成是有用的。     

YZ-1型放射性污染测量仪

为解决对受放射性污染的粮、菜、水和人体排泄物等样品进行快速测定,及时估算放射性污染量,因而设计研制了YZ—1型放射性污染测量仪。它由主机和探头两部份组成,可分别探测β和γ两种射线(必要时亦可探测α射线)的强度。主机采用国产CMOS集成电路、六位数字显示、自动定时、交直流供电,具有体积小、耗电少、计数容量大、灵敏度高、携带和操作维修方便等特点。它也适用于平时对放射性样品的活度测量,是一种军民两用、平战结合的射线测量仪器。     

放射性土壤样品采集不确定度的全程质量控制(SAX)评定方法探讨

采样过程的不确定度是辐射环境监测结果不确定度的一个重要来源,但长期以来,由于采样过程不确定度难以量化,目前辐射环境监测结果的不确定度大都只考虑了分析过程,没有考虑采样过程。利用全程质量控制方法(SAX方法)进行辐射环境监测采样的设计,并采用稳健方差分析方法,可得到采样过程的方差,从而实现对采样过程不确定度的量化。利用该方法进行了一次实际的辐射环境监测,并对土壤样品的结果进行了方差分析,得到了采样不确定度。对监测结果及其不确定度进行了分析,认为SAX方法可以用于指导辐射环境监测,能够进一步优化辐射环境监测方案设计,提高监测质量。     

Software for gamma cameras for mapping radioactive contamination

The software for portable systems for obtaining γ image with coding apertures (masks) is described. The software developed controls all systems that form an image and obtain shadow patterns, reconstructs the initial γ-image, and processes previously obtained images. The software is used with portable systems in which URA and MURA type masks with different rank are used as the coding aperture. Programs for modeling the process of obtaining shadow patterns using real apparatus which has different positionsensitive detectors are described. Possible configurations of new apparatus which could be of practical interest are examined.     

Radiation survey of radioactive objects at the Kirovo-Chepetsk chemical combine

The methods and means for performing a radiation survey of objects and grounds of the Kirovo-Chepetsk Chemical Combine are presented. Results of a survey of rooms in the combine and measurements of soil contamination levels on the grounds and of the specific activity of samples of radioactive wastes in temporary repositories and slag dumps are presented. The surveys make it possible to develop a concept and a project for rehabilitating these objects and grounds and to choose a technology for handling radioactive wastes during liquidation or preservation of repositories.