scholarly journals Scientifi c and Design Aspects of Liquid Radioactive Waste Vitrifi cation from Nuclear Power Plants with WWER-1200 Reactor Units

2020 ◽  
Vol 11 (2) ◽  
pp. 56-65
Author(s):  
V. T. Sorokin ◽  
◽  
D. I. Pavlov ◽  
V. A. Kashcheev ◽  
N. D. Musatov ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Bottom Sediment ◽  
Nuclear Power ◽  
Power Plants ◽  
Liquid Radioactive Waste ◽  
State System ◽  
Radioactive Waste Management ◽  
Industrial Use ◽  
State Of Art

The article presents a comparison of technologies for liquid radioactive waste bottom sediment processing from NPPs with WWER-1200 reactor units. Vitrifi cation and cementing methods were compared based on the state of art in the development of the Unifi ed State System for Radioactive Waste Management, as well as engineering and design study of various processing methods. The research demonstrates that industrial use of the vitrifi cation method can be seen as a promising one when it comes to the processing of liquid radioactive waste from NPPs and radiochemical plants.

An overview of research activities on cementitious materials for radioactive waste management

2012 ◽  
Vol 1475 ◽  
Author(s):  
Zoran Drace ◽  
Irena Mele ◽  
Michael I. Ojovan ◽  
R. O. Abdel Rahman
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Management Practices ◽  
Fuel Cycle ◽  
Large Body ◽  
Cementitious Materials ◽  
Radioactive Waste Management ◽  
Research Activities

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.

Radiological Aspects of Liquid Radioactive Waste Management from Nuclear Power Plant Operation

2017 ◽  
pp. 34-38
Author(s):  
О. Кочетков ◽  
O. Kochetkov ◽  
Е. Иванов ◽  
E. Ivanov ◽  
Д. Шаров ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Liquid Radioactive Waste ◽  
Radiological Hazard ◽  
Treatment Technology ◽  
Radioactive Waste Management ◽  
Waste Characterization ◽  
Radioactive Waste Characterization ◽  
Treatment Technologies

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.

Optimization of Concrete Container Composition in Radioactive Waste Management

1985 ◽  
Vol 50 ◽  
Author(s):  
I. B. Plecas ◽  
Li. L. Mihajlovic ◽  
A. M. Kostadinovic
Keyword(s):  
Mechanical Properties ◽  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Leakage Rate ◽  
Intermediate Level ◽  
Radioactive Waste Management ◽  
Intermediate Level Radioactive Waste

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.

Environmental Risk of Nuclear Power and Policy Proposal on Disposal of Solid Radioactive Waste

2013 ◽  
Vol 726-731 ◽  
pp. 2894-2897
Author(s):  
Jie Liu ◽  
Fang Xin Wei ◽  
Zhuo Wang
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Solid Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Radioactive Waste Management ◽  
Policy Proposal ◽  
Existing Problems ◽  
Waste Storage ◽  
Nuclear Power Development

The difficulty occurred in nuclear power plants that the accumulated radioactive solid waste is beyond the design capacity and unable to be sent to disposal is focused on in this paper. The deep reasons for the difficulty occurred are concluded to be the unclear responsibility for disposal of radioactive waste and the divided national function of nuclear power development and radioactive waste management, by analyzing the disposal demand of radioactive solid waste caused by continuous development of nuclear power and the current situation and existing problems for the disposal of low-intermediate level radioactive solid waste in China. The policy suggestions of issuing the disposal siting plan of radioactive solid waste, forming independent firms of radioactive waste storage and disposal and improving radioactive waste management fund system are proposed based on above analysis and investigation.

scholarly journals Radioactive Waste Management at Ukrainian Nuclear Power Plants. State and Challenges.

2016 ◽  
pp. 41-46
Author(s):  
S. Kondratiev ◽  
H. Borozenets ◽  
I. Yarmosh ◽  
T. Kutuzova ◽  
Yu. Chepurnyi
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Waste Processing ◽  
Radioactive Waste Management ◽  
Advanced Technologies

The paper considers methods and approaches to radioactive waste management used at Ukrainian nuclear power plants and advanced technologies to be applied after completed construction of radioactive waste processing facilities at NPP sites.

scholarly journals Optimisation by mathematical modeling of physicochemical characteristics of concrete containers in radioactive waste management

2013 ◽  
Vol 28 (1) ◽  
pp. 25-30
Author(s):  
Ilija Plecas ◽  
Laslo Nadjdjerdj ◽  
Milos Davidovic
Keyword(s):  
Mathematical Modeling ◽  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Optimal Solution ◽  
Physicochemical Characteristics ◽  
Concrete Composition ◽  
Radioactive Waste Management

A method for obtaining an optimal concrete container composition used for storing radioactive waste from nuclear power plants is developed. It is applied to the radionuclides 60Co, 137Cs, 85Sr, and 54Mn. A set of recipes for concrete composition leading to an optimal solution is given.

The Influence of Chemical Composition of Liquid Radioactive Waste on the Evaporation Process

2000 ◽  
Vol 663 ◽  
Author(s):  
P.P. Poluektov ◽  
L.P. Soukhanov ◽  
M.I. Zhicharev
Keyword(s):  
Nitric Acid ◽  
Chemical Composition ◽  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Liquid Radioactive Waste ◽  
Salt Content ◽  
Evaporation Process ◽  
Simplified Models ◽  
Salt Systems

ABSTRACTA method is suggested to assess the tolerable salt content of the evaporator bottoms from the data on solubility in salt systems taken as simplified models of liquid radioactive waste (LRW) arising from nuclear power plants (NPP) with boiling reactors. It has been demonstrated that the degree of evaporation may be substantially increased by implementing the process in nitric acid. Equations have been derived that allow the calculation of the minimum needed acidity of the solution to allow maximum evaporation.

Cold Crucible Vitrification of NPP Operational Waste

2002 ◽  
Vol 757 ◽  
Author(s):  
Feodor A. Lifanov ◽  
Michael I. Ojovan ◽  
Sergey V. Stefanovsky ◽  
Rudolf Burcl
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Glass Melting ◽  
Liquid Radioactive Waste ◽  
Specific Radioactivity ◽  
Melting Process ◽  
Specific Power ◽  
Cold Crucible ◽  
Minimal Impact

ABSTRACTOperational radioactive waste is generated during routine operation of nuclear power plants (NPP). This waste must be solidified in order to ensure safe conditions of storage and disposal. Vitrification of NPP operational waste is a relative new solidification option being developed for last years. The vitrification technology comprises a few stages, starting with evaporation of excess water from liquid radioactive waste, followed by batch preparation, glass melting, and ending with vitrified waste blocks and some relative small amounts of secondary waste. Application of induction high frequency cold crucible type melters facilitates the melting process and significantly reduces the generation of secondary waste. Two types of glasses were designed in order to vitrify operational waste depending on the reactor type at the NPP. For the NPP with RBMK-type reactors the glass 16.2Na2O 0.5K2O 15.5CaO 2.5 Al2O3 1.7Fe2O3 7.5B2O3 48.2SiO2 1.1 Na2SO4 1.2NaCl (5.7 others) was produced. For NPP with WWER reactors the glass 24.0Na2O 1.9K2O 6.2CaO 4.3Al2O3 1.8Fe2O3 9.0B2O3 46.8SiO2 0.8Na2SO4 0.9NaCl (4.3 others) was produced. The melting temperatures of both glass formulations were 1200–1250 C, specific power consumption was 5.2 ± 0.8 kW h/kg, 137Cs loss was within the range 3 - 4 %. The specific radioactivity of glass reached 7.0 MBq/kg. Glass blocks obtained were studied both in laboratory and field conditions. Long-term studies revealed that vitrified NPP operational waste has the minimal impact onto environment. Since the glass has excellent resistance to corrosion it gives the basic possibility of maximal simplification of engineered barrier systems in a disposal facility. The simplest disposal option for vitrified NPP waste is to locate the packages directly into earthen trenches provided the host rock has the necessary sorption and confinement properties.

scholarly journals Radioactive Waste Management of Fusion Power Plants

10.5772/35045 ◽  
2012 ◽  
Author(s):  
Luigi Di ◽  
Laila El-Guebaly ◽  
Boris Kolbasov ◽  
Vincent Massaut ◽  
Massimo Zucchetti
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Power Plants ◽  
Radioactive Waste Management ◽  
Fusion Power
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