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

Author(s):  
P. Degnan ◽  
I. Mele ◽  
P. Dinner ◽  
H. Monken-Fernandes ◽  
A. Morales Leon ◽  
...  

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.

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):  
P. Poskas ◽  
J. E. Adomaitis ◽  
R. Kilda

The growing number of radionuclide applications in Lithuania is mirrored by increasing demands for efficient management of the associated radioactive waste. For the effective control of radioactive sources a national authorization system based on the international requirements and recommendations was introduced, which also includes keeping and maintaining the State Register of Sources of lonising Radiation and Occupational Exposure. The principal aim of the Lithuania’s Radioactive Waste Management Agency is to manage and dispose all radioactive waste transferred to it. Radioactive waste generated during the use of sources in non-power applications are managed according to the basic radioactive waste management principles and requirements set out in the Lithuanian legislation and regulations. The spent sealed sources and other institutional waste are transported to the storage facilities at Ignalina NPP. About 35,000 spent sealed sources in about 500 packages are expected until year 2010 at Ignalina NPP storage facilities. The existing disposal facility for radioactive waste from research, medicine and industry at Maisiagala was built in the early 1960’s according to a concept typical of those applied in the former Soviet Union at that time. SKB (Sweden) with participation of Lithuanian Energy Institute has performed assessment of the long-term safety of the existing facility. It was shown that the existing facility does not provide safe long-term storage of the waste already disposed in the facility. Two alternatives were defined to remedy the situation. A first alternative is the construction of a surface barrier and a second one is a retrieval solution, whereby the already stored waste will be retrieved for conditioning, characterisation and interim storage at Ignalina NPP. Facilities for the processing of the institutional radioactive waste are required before submittal to Ignalina NPP for storage, since the present facilities are inadequate. Feasibility study to establish a new central facility has been performed by SKB International Consultants (Sweden) with participation of Lithuanian Energy Institute. This study has identified the process applied and equipment needed for a new facility. Reference design and Preliminary Safety Assessment have also been performed. Plans for the interim storage and disposal of the institutional waste are described in the paper. The aspects of finging safe disposal solutions for spent sealed sources in a near surface repositories are also discussed.


Author(s):  
Ja´n Horva´th ◽  
Dusan Krasny

The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske´ Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented.


Author(s):  
Mick Bacon ◽  
Doug Ilett ◽  
Andy Whittall

In 2006 the UK Governments response to recommendations by its Committee on Radioactive Waste Management (CoRWM) established, in England and Wales, that geological disposal, supported by safe and secure interim storage, is the preferred route for the long-term management of higher-activity radioactive waste (i.e. that which is not suitable for near-surface disposal). It also gave the responsibility for delivering the programme for a deep geological repository to the Nuclear Decommissioning Authority (NDA). The Scottish Government has a policy of long term, near site, near surface safe and secure interim storage. To support the open and transparent approach promised by Government, the Health and Safety Executive (HSE), the Environment Agency and the Scottish Environment Protection Agency (SEPA) are developing joint guidance on the management of higher-activity radioactive waste to explain regulatory objectives in securing safe and secure interim storage and the associated management of radioactive wastes. The guidance comes in two parts: • Guidance on the regulatory process; • Technical guidance modules. The guidance promotes a cradle to grave approach to radioactive waste management and by aligning the regulatory interests of environmental and safety regulators it delivers one of the Government’s “Better Regulation” objectives. This paper describes the process by which the joint guidance was produced with particular emphasis on stakeholder engagement. It describes the key features of the guidance, including the concept of the radioactive waste management case (RWMC). Finally the problems encountered with dissemination and implementation are discussed together with measures taken by the regulators to improve these aspects.


MRS Advances ◽  
2020 ◽  
Vol 5 (5-6) ◽  
pp. 275-282 ◽  
Author(s):  
Vsevolod Igin ◽  
Victor Krasilnikov

Abstract:The paper provides generic overview of legal and regulatory framework of radioactive waste management activities held in Russian Federation and national operator responsibilities and accomplishments. It gives a short description of waste classification scheme used and plans for radioactive waste disposal. In particular the paper provides information on the plans of the FEDERAL STATE UNITARY ENTERPRISE "National operator for radioactive waste management" to construct and operate several near-surface disposal facilities for low and intermediate level waste with total capacity up to 550 000 cubic meter. The paper also provides detailed information on the steps of high-level waste disposal program including site-selection, construction phase of the underground research laboratory (URL) near the city of Zheleznogorsk, Krasnoyarsk Region and research program after the construction of the URL. The paper also describes Russian system and state policy in the field of RW management and gives recommendations for future implementers.


1994 ◽  
Vol 5 (3) ◽  
pp. 255-275
Author(s):  
R.D. Little ◽  
P.R. Maul ◽  
G.M. Smith ◽  
P.A. Towler

Comparisons have been frequently drawn between the radioactive and hazardous waste industries. However, they have tended to focus on particular aspects of the industries rather than the totality of waste management practices. In this paper a “cradle to grave” approach is taken, summarising and comparing practices in the two industries at all stages of the waste management cycle in OECD countries. In these countries there has been a convergence of approaches in recent years, with the hazardous waste industry now employing many of the practices which were developed for radioactive waste at a much earlier date. There is increasing emphasis on waste minimisation and volume reduction in both areas, and near surface engineered disposal facilities for the two types of waste now share many common features. The most notable outstanding difference between the two industries is the timescales of concern considered in post-disposal performance assessments. For radioactive waste, the impacts of disposal have been considered for timescales of many thousands, or even millions, of years into the future. The question of whether it is necessary to consider environmental impacts over such extended periods is only now becoming an issue for hazardous wastes.


2015 ◽  
Vol 6 (2) ◽  
pp. 86-95
Author(s):  
John Tauxe

Much of humanity's solid waste will outlast the human race, and the waste generated by one generation must be endured and managed by future societies. Radioactive wastes are unique in that their regulation explicitly considers the protection of future generations. But radioactive waste management faces a serious quandary: how to balance the substantial expense of waste isolation against the uncertain mitigation of risks to hypothetical future humans. Most of this uncertainty stems not from natural processes, or from the projected performance of engineered materials, but rather from social actions and human behaviors. Given that these uncertainties become overwhelming when consider the future only a few centuries from now, how far into the future is it useful for us to attempt to assess risks? Government regulators are currently grappling with this question as they rewrite regulations in order to accommodate radioactive wastes that have the potential for unacceptable and perpetual human health risks. This paper discusses the issues surrounding the period of performance expected from radioactive waste management practices, and outlines central conditions for soundly addressing controversial problems.


2012 ◽  
Vol 1475 ◽  
Author(s):  
Elvira Rosa Maset

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.


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