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.

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.

Advancing the Use of IAEA Networks in Radioactive Waste Management: Past Successes, Present Challenges and Future Opportunities

2010 ◽  
Author(s):  
P. Degnan ◽  
I. Mele ◽  
P. Dinner ◽  
H. Monken-Fernandes ◽  
A. Morales Leon ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Management Practices ◽  
Fuel Cycle ◽  
Support Network ◽  
Radioactive Waste Management ◽  
Member States ◽  
Near Surface ◽  
Novel Technologies ◽  
Stage Of Development

Since 2001 the International Atomic Energy Agency has championed the concept and use of Networks to advance radioactive waste management across the globe. At the present time there are four Networks managed on behalf of Member States by the IAEA and a fifth one is currently being implemented. The scopes of interest covered by the Networks encompass near-surface and deep geological disposal, the decommissioning of nuclear facilities, the environmental remediation of sites contaminated with radioactive materials and the characterisation of low- and intermediate-level radioactive wastes. To date over 100 organisations from more than 40 Member States are involved in the Networks. Many of these Network participants generously donate resources, time and effort to support Network activities, while others with nascent or otherwise less well developed programmes are still in the process of acquiring experience, capabilities and know-how. Regardless of the stage of development, all Network participants share in the mutual benefits that arise from improved communications with sister organisations and the sharing of experience and knowledge. The universal Goal of the Networks is the promotion of methods and technologies that will enhance the safety and sustainability of radioactive waste management practices and facilities. This Goal is being achieved through continuous improvements in communication and knowledge sharing between Network participants and the provision of enhanced opportunities for training, involvement in demonstration projects and the development of novel technologies and methodologies. We recognise that interdisciplinary understanding and the coordination of efforts at key interfaces at the back-end of the fuel cycle are critical aspects for achieving the Network Goal efficiently and effectively. Consequently, the IAEA Networks that will be operational by the end of 2010 are themselves are being molded into an organic “Network of Networks” where the use of new electronic media and the possibilities presented by enhanced communication channels will be exploited. Here we provide an overview of the IAEA Networks in radioactive waste management and present a new tool that is under development, an internet-based portal for enhanced communications and the provision of improved training opportunities.

Radioactive Waste and Spent Fuel Management in Argentina

2012 ◽  
Vol 1475 ◽  
Author(s):  
Elvira Rosa Maset
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Environmental Remediation ◽  
Power Plants ◽  
Fuel Cycle ◽  
Atomic Energy Commission ◽  
Atomic Energy ◽  
Spent Fuel ◽  
Radioactive Waste Management ◽  
Management Regime

ABSTRACTSince its creation in 1950, the Argentine Atomic Energy Commission (CNEA), has worked on the development of applications for the peaceful use of nuclear energy. They include, among others, research and development activities in basic and nuclear technology areas, the operation of important facilities for the production of radioisotopes and the performance of tasks in connection with the nuclear fuel cycle, mining and uranium processing activities, manufacturing of fuel elements, production of heavy water and the operation of two nuclear power plants. Also demonstrating reprocessing programs have been developed.As a result of the above mentioned activities performed in the nuclear field by private and public entities, various types of radioactive waste have been and are produced during operation and maintenance of facilities and plants, and will be produced in their future decommissioning. CNEA is also responsible for the environmental remediation of the closed uranium mining and milling facilities and for the management of disused sealed sources from medical and industrial applications.Activities concerning radioactive waste management are carried on according not only to Nuclear Regulatory Authority requirements and International Atomic Energy Agency recommendations, but also to the national legal framework.The Law Nº 25.018, "Radioactive Waste Management Regime“(1998), created the National Program for Radioactive Waste Management (PNGRR), as part of CNEA organization.

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.

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.

Regulatory Research for Geological Disposal of High-Level Radioactive Waste in Japan

2010 ◽  
Author(s):  
Shinichi Nakayama ◽  
Yoshio Watanabe ◽  
Masami Kato
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Regional Scale ◽  
Industrial Safety ◽  
Future Research ◽  
Radioactive Waste Management ◽  
Geological Disposal ◽  
Research Activities ◽  
Research Institutes ◽  
Research Plan

The Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade and Industry (NISA) has renewed its regulatory role and its need for regulatory research on radioactive waste management, with recent circumstances of radioactive waste management in Japan being taken into consideration. In response, a technical supporting organization, the Japan Nuclear Energy Safety Organization (JNES), in 2009 released the five-year research plan “Regulatory Research Plan on Radioactive Waste Management 2010–2014”, in cooperation with the research institutes of the Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST). The geological disposal research plan and the future research activities are outlined in this paper. JNES launched safety studies on geological disposal in 2003, the year it was established. JAEA and AIST joined as regulatory support research institutes in 2005. In October 2007, all three parties signed an agreement of cooperative study on geological disposal, which facilitated joint studies and exchanges of staff, data, and results. One of the ongoing joint studies has focused on regional-scale hydrogeological modeling using JAEA’s Horonobe Underground Research Laboratory.

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