scholarly journals Exploring the Dialogical Space of Hybrid Forums: The “Predictably Unpredictable” Case of Radioactive Waste Management in Denmark, 2003-2018

2019 ◽  
Vol 39 (1-2) ◽  
pp. 4-18
Author(s):  
Rosa Nan Leunbach ◽  
Kristian H. Nielsen

Denmark was once at the forefront of nuclear research, operating three experimental nuclear reactors at the research facility at Risø, close to Copenhagen. However, the 1985 resolution of the Danish Parliament excluded nuclear power from the national energy mix. In 2003, the Parliament passed a resolution on the decommissioning of the nuclear facility at Risø, including plans for establishing a permanent solution for radioactive waste management. To understand the ensuing socio-technical controversy, we employ the “hybrid forum” framework that emphasizes the entangled political-epistemological role of the municipalities and protest groups. They mobilized political resistance while also performing “research in the wild.” In 2016, the protest groups became part of an institutionalized “hybrid forum” where they could negotiate directly with experts and government representatives. We conclude that municipalities and protest groups were instrumental in changing the Danish position on radioactive waste management from final repository to long-term storage at Risø.

Author(s):  
Hans Code´e ◽  
Ewoud Verhoef

Time will render radioactive waste harmless. How can we manage the time radioactive substances remain harmful? Just ‘wait and see’ or ‘marking time’ is not an option. We need to isolate the waste from our living environment and control it as long as necessary. For the situation in the Netherlands, it is obvious that a period of long term storage is needed. Both the small volume of waste and the limited financial possibilities are determining factors. Time is needed to let the volume of waste grow and to let the money, needed for disposal, grow in a capital growth fund. An organisation such as COVRA — the radioactive waste organisation in the Netherlands — can only function when it has good, open and transparent relationship with the public and particularly with the local population. If we tell people that we safely store radioactive waste for 100 years, they often ask: “That long?” How can we explain the long-term aspect of radioactive waste management in a way people can relate to? In this paper, an overview is given of the activities of COVRA on the communication of radioactive waste management.


Author(s):  
Zoran Drace ◽  
Michael I. Ojovan

The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in 2007 [1, 2]. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste management system with various purposes and included waste packages, wasteforms and backfills as well as investigation of interactions and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields); (vii) testing and nondestructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria for waste packages, waste forms and backfills; transport, long term storage and disposal requirements; and finally (ix) modelling or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling, especially in the post-closure phase. The CRP has gathered overall 26 research organizations from 22 Member States aiming to share their research and practices on the use of cementitious materials [2]. The main research outcomes of the CRP were summarized in a summary report currently under preparation to be published by IAEA. The generic topical sections covered by report are: a) conventional cementitious systems; b) novel cementitious materials and technologies; c) testing and waste acceptance criteria; and d) modelling long term behaviour. These themes as well as all contributions of participating organizations were further developed in the individual reports to be presented in the IAEA publication. The CRP facilitated the exchange of information and research co-operation in resolving similar problems between different institutions and contributed towards improving waste management practices, their efficiency and general enhancement of safety.


Author(s):  
Ian Upshall

The creation and subsequent access to accurate information is widely accepted as a vital component of a national radioactive waste management strategy. Information on the origin and quantity of the waste together with its physical, chemical and radiological characteristics provides a catalyst for sound and transparent decision making. This information will originate from a number of potentially disparate sources, including material manufacturers, facility operators, waste producers, Government and Non-Government organisations and regulators. The challenge to those with a role in information management in further increased by the fact that much of the information created is required to support activities, not only in the immediate future, but also in the longer-term — typically many decades or even centuries. The International Atomic Energy Agency (IAEA) has published a number of guidance documents under the Safety Series, one of which makes direct reference to information management. The document [1] is intended to assist Member States in the development of a national system for radioactive waste management and identifies the key responsibilities and essential features of such a system. The following statement appears in Section 5: “The regulatory body, the waste generators and the operators of radioactive waste management facilities should maintain documentation and records consistent with the legal requirements and their own needs.” An essential requirement of these ‘documents and records’ is that they should be “...kept in a condition that will enable them to be consulted and understood later by people different from, and possibly without reference to, those who generated the records ...” The scope of the documentation and records to be kept will be wide ranging but will include “...an inventory of radioactive waste, including origin, location, physical and chemical characteristics, and, as appropriate a record of radioactive waste removed or discharged from a facility”, and “site plans, engineering drawings, specifications and process descriptions ... radioactive waste package identification ...”. It is has long been recognised in the United Kingdom that the management of radioactive waste will require the assembly and secure retention of a diversity of records and data. This information will be needed to inform the strategic decision making process, thus contributing to the future safe, environmentally sound and publicly acceptable management of radioactive waste. In the meantime it will also service the nation’s international commitments. When the planning application for a Rock Characterisation Facility (RCF) was refused and the subsequent Nirex appeal rejected in 1997, it was recognised that transfer of waste to a national repository was ulikely to take place for many decades. The long-term preservation of information by the waste management organisations thus became an issue. Since this time, the UK nuclear industry, including the waste producers, regulators and other Government Departments have worked together to develop a common information management system that is now being implemented. It is based on an Oracle database and is supported by ‘electronic tools’ designed to facilitate entry and retrieval of data in a common format. Long-term access to these data underpins many aspects of the system design. Designing such a system and seeing through its development has been a challenge for all those involved. However, as the project nears the completion of the development phase, it is clear there are several benefits in this approach. These include a sharing of best practice, shared development costs, an improved understanding of the needs of all parties, and the use of a common platform and tools. The ‘partnership approach’ between waste management organisations, Government departments and regulators will also reduce the likelihood of future surprises or conflicts of interest. Industry-wide co-operation also provides a greater degree of confidence that the system will continue to enjoy technical and financial support for the foreseeable future. The British Radwaste Information Management System (BRIMS) is supported by the principal waste producers, the Department for Environment, Food and Rural Affairs (DEFRA), the Nuclear Installations Inspectorate (NII) and United Kingdom Nirex Limited (Nirex). All organisations that have participated in its development over the past seven years have free access to it and may use it as part of their waste management strategy.


Author(s):  
Jorge Lang-Lenton Leo´n ◽  
Emilio Garcia Neri

Since 1984, ENRESA is responsible of the radioactive waste management and the decommissioning of nuclear installations in Spain. The major recent challenge has been the approval of the Sixth General Radioactive Waste Plan (GRWP) as “master plan” of the activities to be performed by ENRESA. Regarding the LILW programme, the El Cabril LILW disposal facility will be described highlighting the most relevant events especially focused on optimizing the existing capacity and the start-up of a purpose–built disposal area for VLLW. Concerning the HLW programme, two aspects may be distinguished in the direct management of spent fuel: temporary storage and long-term management. In this regards, a major challenge has been the decision adopted by the Spanish Government to set up a Interministerial Committee for the establishment of the criteria that must be met by the site of the Centralized Intermediate Storage (CTS) facility as the first and necessary step for the process. Also the developments of the long-term management programme will be presented in the frame of the ENRESA’s R&D programme. Finally, in the field of decommissioning they will be presented the PIMIC project at the CIEMAT centre and the activities in course for the decommissioning of Jose´ Cabrera NPP.


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):  
Fouad Al-Musawi ◽  
Emad S. Shamsaldin ◽  
John R. Cochran

The government of Iraq, through the Ministry of Science and Technology (MoST) is decommissioning Iraq’s former nuclear facilities. The 18 former facilities at the Al-Tuwaitha Nuclear Research Center near Baghdad include partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. These 18 former facilities contain large numbers of silos and drums of uncharacterized radioactive waste and approximately 30 tanks that contain or did contain uncharacterized liquid radioactive wastes. Other key sites outside of Al Tuwaitha include facilities at Jesira (uranium processing and waste storage facility), Rashdiya (centrifuge facility) and Tarmiya (enrichment plant). The newly created Radioactive Waste Treatment Management Directorate (RWTMD) within MoST is responsible for Iraq’s centralized management of radioactive waste, including safe and secure disposal. In addition to being responsible for the uncharacterized wastes at Al Tuwaitha, the RWTMD will be responsible for future decommissioning wastes, approximately 900 disused sealed radioactive sources, and unknown quantities of NORM wastes from oil production in Iraq. This paper presents the challenges and progress that the RWTMD has made in setting-up a radioactive waste management program. The progress includes the establishment of a staffing structure, staff, participation in international training, rehabilitation of portions of the former Radioactive Waste Treatment Station at Al-Tuwaitha and the acquisition of equipment.


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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