Radiation pollution as a threat to the environmental security of the Russia

2022 ◽  
pp. 101-108
Author(s):  
E. A. Sharyapova ◽  
A. V. Shuvaev ◽  
I. O. Zhavoronkova

The topic of the article is relevant — the problem of radioactive waste management, since the task of increasing the level of security of organizations of the country’s nuclear power-industrial complexes is one of the priorities for ensuring state and public security in the National Security Strategy of the Russian Federation. The growth of radioactive waste is a hazard to human health and the environment. The state needs a unified regulation of the radioactive waste management policy and prevention of radioactive disasters.

2012 ◽  
Vol 1475 ◽  
Author(s):  
Pablo Zuloaga ◽  
Julio Astudillo

ABSTRACTSpanish Radioactive Waste Management policy is established by the Government and implemented by ENRESA. The General Plan (GRWP) covers the analysis of the actual and foreseen inventories of spent fuel and all categories of radioactive waste, their present situation, the management strategy and actions identified, as well as funding and financial provisions. Very Low (VLLW) and Low and Intermediate Level Waste (LILW) are disposed of at El Cabril facility, which has two separate disposal areas: one intended for VLLW, based on clay and polyethylene and started up in 2006; and one for LILW conditioned in retrievable concrete containers, commissioned in 1992. Spent fuel (SF) is being stored in pools and in two dry storage installations. The priority is the development of the SF and HLW centralized storage facility. In 2009, the Government launched a call for candidate municipalities, in a public, participative process. In September 2010 a report was sent to the Cabinet, proposing eight volunteer communities, four of them deemed preferred. In the 90’s a deep geological repository (DGR) site identification program was carried out. DGR basic designs and associated performance assessments were developed in three rock types. ENRESA has set a research program that includes research projects in order to strengthen the link between management and scientific basis and improve the performance assessment, directed to the behavior of barriers, fuel or waste forms in different storage and final disposal conditions, and characterization techniques. There is also a participation in connected fields or supporting decision-making, such as advanced separation and transmutation.


1982 ◽  
Vol 15 ◽  
Author(s):  
F S Feates ◽  
H J Richards

ABSTRACTIn the United Kingdom the responsibility for radioactive waste management policy lies with the environmental Ministers. The Department of the Environment is also responsible in England for authorisation of all radioactive waste disposal activities and has its own Radiochemical Inspectorate to ensure that government policy is implemented. An independent Radioactive Waste Management Advisory Committee reports directly to the Secretary of State for the Environment.Low-level wastes are currently disposed of by shallow burial or to the deep ocean. Sites for the disposal of intermediate-level wastes are being sought as a matter of urgency and heat-emitting, reprocessing wastes will be stored on the surface for at least fifty years. The rationale of this policy is explained.


2012 ◽  
Vol 1475 ◽  
Author(s):  
Zoran Drace ◽  
Irena Mele ◽  
Michael I. Ojovan ◽  
R. O. Abdel Rahman

ABSTRACTAn overview is given on research activities on cementitious materials for radioactive waste management systems based on the IAEA Coordinated Research Project (CRP) held in 2007-2010. It has been joined by 26 research organizations from 22 countries which shared their research and practical activities on use of cementitious materials for various barrier purposes. The CRP has initially formulated the research topics considered within four specific streams: A) Conventional cementitious systems; B) Novel cementitious materials and technologies; C) Testing and waste acceptance criteria; and D) Modelling long term behaviour.The CRP has analysed both barrier functions and interactions envisaged between various components with focus on predisposal stage of waste management. Cementation processes have achieved a high degree of acceptance and many processes are now regarded as technically mature. A large body of information is currently available on proven waste conditioning technologies although novel approaches are continuing to be devised.Most of the existing technologies have been developed for conditioning of large amounts of operational radioactive waste from nuclear power plants and other nuclear fuel cycle facilities. However new waste streams including those resulting from legacy and decommissioning activities required improved material performance and technologies.The most important outcome of CRP was the exchange of information and research co-operation between different institutions and has contributed towards general enhancement of safety by improving waste management practices and their efficiency. The paper presents the most important results and trends revealed by CRP participants. The research contributions of participating organizations will be published as country contributions in a forthcoming IAEA technical publication.


Author(s):  
О. Кочетков ◽  
O. Kochetkov ◽  
Е. Иванов ◽  
E. Ivanov ◽  
Д. Шаров ◽  
...  

Purpose: The prospects and scale of the further development of nuclear energy depend to a large extent on the solution of the radioactive waste management (RW) problem. Special attention is given to management of the liquid radioactive waste (LRW), which poses the main potential hazard to the public and the environment, since LRW storage can lead to leaks into the environment. The purpose of the paper is to examine the radiological aspects of LRW management from nuclear power plants (NPPs) operation and to study the influence of the list of radionuclides controlled in RW on the evaluation of the efficiency of LRW treatment technology and on the validity of radioactive waste characterization and classification. Material and methods: The work is based on analysis of public materials (scientific publications, legal documents, international standards, recommendations of international organizations) in the area of LRW treatment and conditioning technologies, and methods of radioactive waste characterization, including information about accepted lists of controlled radionuclides. Results: It is shown that an unreasonable reduction of the list of controlled radionuclides can lead to a significant underestimation of the radiological hazard of RW packages transferred for disposal. In order to optimize the volume of RW radiation control, the radionuclide vector technology was proposed. It is stated that the technology is not universal and its application in each specific case requires additional justification. It is shown that the correctness of accounting for the radiological characteristics of radioactive waste can significantly influence the evaluation of the efficiency of the radioactive waste treatment technology. A possible approach to determining the acceptability of LRW treatment technology based on the characteristics of the final products formed is suggested. Conclusions: There is no universal approach to solve the problems of LRW treatment at the moment. A survey of the characteristics of LRW (chemical, physical, radiation) accumulated and formed during the operation of NPP with various types of reactors (VVER, RBMK, BN) should be performed to determine the initial requirements for LRW treatment technologies. A comprehensive analysis of the efficiency of LRW treatment technologies at all Russian NPPs is of interest with taking into account radionuclides that determine the radiological hazard of radioactive waste after the final disposal.


1985 ◽  
Vol 50 ◽  
Author(s):  
I. B. Plecas ◽  
Li. L. Mihajlovic ◽  
A. M. Kostadinovic

AbstractIn this paper an optimization of concrete container composition, used for storing low and intermediate level radioactive waste from nuclear power plants in Yugoslavia, is presented.Mechanical properties 37−52 MPa, permeability 1.07. 10−13 - 1.50. 10−11cm2 and leakage rate 3.66. 10−6 - 1.77. 10−4 cm/d for concrete made of commercial materials, were tested.


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