Enlargement of the Baldone Near-Surface Radioactive Waste Repository

2007 ◽  
Author(s):  
A. Dreimanis
Keyword(s):  
Public Education ◽  
Radioactive Waste ◽  
Negative Attitude ◽  
Radiation Level ◽  
Near Surface ◽  
The Public ◽  
Long Term Storage ◽  
Compensation Mechanisms ◽  
Technical Features

A unified analysis of the enlargement of the Baldone near-surface radioactive waste (RW) repository RADONS considers the interplay of the existing engineering, safety and infrastructure premises, with the foreseen newly socio-technical features. This enlargement consists in construction of two additional RW disposal vaults and in building a long-term storage facility for spent sealed sources at the RADONS territory. Our approach is based on consecutive analysis of following basic elements: - the origin of enlargement – the RADONS safety analysis and a set of optimal socio-technical solutions of Salaspils research reactor decommissioning waste management; - the enlargement – a keystone of the national RW management concept, including the long-term approach; - the enlargement concept – the result of international co-operation and obligations; - arrangement optimization of new disposal and storage space; - environmental impact assessment for the repository enlargement – the update of socio-technical studies. The study of the public opinion revealed: negative attitude to repository enlargement is caused mainly due to missing information on radiation level and on the RADONS previous operations. These results indicate: basic measures to improve the public attitude to repository enlargement: the safety upgrade, public education and compensation mechanisms. A detailed stakeholders engagement and public education plan is elaborated.

Long-Term Storage and Radioactive Waste Retrieval from Historical Radon-Type Storage Facility

MRS Advances ◽  
2019 ◽  
Vol 5 (5-6) ◽  
pp. 283-291
Author(s):  
Alexander Smetnik
Keyword(s):  
Radioactive Waste ◽  
Safety Assessment ◽  
Practical Experience ◽  
Storage Facility ◽  
Effective Management ◽  
Near Surface ◽  
Long Term Storage ◽  
Site Characteristics ◽  
Term Storage

ABSTRACTWithin the framework of the IAEA project “CRAFT” (2011-2014), specialists of JSC “VO “Safety” participated in working group “Safety assessment of the Radon-type facilities”. The IAEA GSG-3 methodology was used in order to address the issue of safety assessment of radioactive waste removal from historical near-surface storage facility of the Radon type. SAFRAN tool (Sweden) was used for safety assessment of a historical Radon type storage facility. Practical experience of SAFRAN application has shown that it can play a significant role in managing records and knowledge on radioactive waste, nuclear facility site, characteristics of geological environment and safety barriers. It can provide reliable long-term storage and effective management of safety related records for the purposes of safety reassessments, review and supervision.

Management of Institutional Radioactive Waste in Lithuania

2003 ◽  
Author(s):  
P. Poskas ◽  
J. E. Adomaitis ◽  
R. Kilda
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Former Soviet Union ◽  
Effective Control ◽  
Surface Barrier ◽  
Radioactive Waste Management ◽  
Near Surface ◽  
Interim Storage ◽  
Storage Facilities

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.

Towards Solving the Problems of the Solid Radioactive Wastes From Decommissioned Soviet-Designed Nuclear Submarines

2007 ◽  
Author(s):  
Bjo̸rn Borgaas ◽  
Ingar Amundsen ◽  
Ole Reistadt
Keyword(s):  
Radioactive Waste ◽  
Nuclear Safety ◽  
Long Term Storage ◽  
Bilateral Agreement ◽  
Solid Radioactive Waste ◽  
The Individual ◽  
Waste Handling ◽  
Term Storage ◽  
Shipyard Workers

This paper describes the cooperation and inspection arrangements for verifying the dismantlement of non-strategic Russian submarines, including waste handling, in accordance with the provisions given in the bilateral agreement between the Governments of Russia and Norway and the Norwegian Plan of Action for Nuclear Safety. The main concerns during the project implementation are nuclear safety, the individual safety of workers and the safe and secure handling of radioactive and toxic wastes. Based on data provided by the shipyard on individual exposure, one dismantlement project results in average in an effective dose for shipyard workers between 1,1 and 1,9 mSv, depending on the scope of the work for each worker. The main conclusion is that the present handling of solid radioactive waste is not optimal as such waste now is being put into the reactor compartments without the possibility for adequate control, including the retrieval for repacking or transfer to adequate storage facilities, after the reactor compartments have been placed in the long term storage facility in Saida Bay. Today there is no repository in Northwest-Russia for defence-related radioactive waste.

Decommissioning and Dismantling Solution Development for Volodarsky Civil Nuclear Fleet Support Ship

2009 ◽  
Author(s):  
Konstantin N. Koulikov ◽  
Rinat A. Nizamutdinov ◽  
Andrey N. Abramov ◽  
Anatoly I. Tsubanikov
Keyword(s):  
Radioactive Waste ◽  
Radiation Safety ◽  
Pollution Source ◽  
Long Term Storage ◽  
Murmansk Region ◽  
State Corporation ◽  
Solid Radioactive Waste ◽  
Federal Special Purpose Program ◽  
Term Storage

Having about 200 tons of solid radioactive waste aboard, the Volodarskiy Floating Technical Base (FTB) is a potential radiation pollution source for the Murmansk region and Kola Bay, as her long-term berthing negatively affects the hull structures. Thereby, Atomflot collaborated with ANO Aspect-Konversia and JSC NIPTB Onega within the frameworks of Federal Special-purpose Program “Assurance of Nuclear and Radiation Safety for 2008 and for the period up to 2015” and developed the Volodarskiy FTB dismantling concept. In 2008 in the course of development of the Volodarskiy FTB dismantling concept the following works were carried out: 1) vessel condition survey, including SRW radiological analysis; 2) feasibility study of the Volodarskiy FTB dismantling alternatives. In this regard the following alternatives were analyzed: – formation of the package assembly in the form of vessel’s undivided hull for durable storage in the Saida long-term storage facility (LTSF); - formation of individual SRW package assemblies for durable storage in the Saida LTSF; - comprehensive recycling of all solid radioactive waste by disposal in protective containers. 3) selection and approval of the dismantling alternative. The alternative of formation of individual SRW package assemblies for durable storage in the Saida LTSF was selected by the Rosatom State Corporation. In this case the works will be performed on a step-by-step basis at the Atomflot enterprise and SRE Nerpa. The conceptual dismantling technology was developed for the selected Volodarskiy FTB dismantling option. The proceedings contain description of options, analysis procedure and proposal for further study of mentioned challenge.

Radioactive Waste: Show Time?

2009 ◽  
Author(s):  
Hans Code´e ◽  
Ewoud Verhoef
Keyword(s):  
The Netherlands ◽  
Radioactive Waste ◽  
Waste Management ◽  
Local Population ◽  
Living Environment ◽  
Radioactive Waste Management ◽  
Long Term Storage ◽  
Capital Growth ◽  
And Control

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.

The Cige´o Industrial Geological Repository Project

2011 ◽  
Author(s):  
Thibaud Labalette ◽  
Alain Harman ◽  
Marie-Claude Dupuis
Keyword(s):  
Radioactive Waste ◽  
Phase 1 ◽  
Public Debate ◽  
Territorial Development ◽  
The Public ◽  
The Future ◽  
Geological Formation ◽  
Local Actors ◽  
High Level

The Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and investigations on the siting and design of the new repository upon the French Radioactive Waste Management Agency (Agence nationale pour la gestion des de´chets radioactifs – Andra), in order for the review of the creation-licence application to start in 2015 and, subject to its approval, the commissioning of the new repository in 2025. In late 2009, Andra submitted to the French government proposals concerning the implementation and the design of Cige´o (Centre industriel de stockage ge´ologique). A significant step of the project was completed with the delineation of an interest zone for the construction of the repositor’s underground facilities in 2010. This year, Andra has launched a new dialogue phase with local actors in order to clarify the implementation scenarios on the surface. The selected site will be validated after the public debate that is now scheduled for the first half of 2013. This debate will be organized by the National Public Debate Committee (Commission nationale du de´bat public). In parallel, the State is leading the preparation of an territorial development scheme, which will be presented during the public debate. The 2009 milestone also constitutes a new step in the progressive design process of the repository. After the 1998, 2001 and 2005 iterations, which focused mainly on the long-term safety of the repository, the Dossier 2009 highlighted its operational safety, with due account of the non-typical characteristics of an underground nuclear facility. It incorporates the first results of the repository-optimisation studies, which started in 2006 and will continue in the future. The reversibility options for the repository constitute proposals in terms of added flexibility in repository management and in package-recovery levels. They orient the design of the repository in order to promote those reversibility components. They contribute to the dialogue with stakeholders in the preparation of the public debate and of the future act on the reversibility conditions of the repository. The development of the repository shall be achieved over a long period, around the century. Hence, the designer will acquire additional knowledge at every new development of the project, notably during Phase 1, which he may reuse during the following phase, in order, for instance, to optimise the project. This process is part of the approach proposed by Andra in 2009 pursuant to the reversibility principle.

Cementitious Materials for Radioactive Waste Management Within IAEA Coordinated Research Project

2011 ◽  
Author(s):  
Zoran Drace ◽  
Michael I. Ojovan
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Cementitious Materials ◽  
Radioactive Waste Management ◽  
Long Term Storage ◽  
Waste Immobilization ◽  
Materials Used ◽  
Cementitious Systems ◽  
Term Storage

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.

NUMO’s Open Solicitation of Volunteer Municipalities for a Potential Disposal Site

2003 ◽  
Author(s):  
Kazumi Kitayama
Keyword(s):  
Radioactive Waste ◽  
Preliminary Investigation ◽  
Disposal Site ◽  
Nuclear Waste Management ◽  
The Public ◽  
Construction Operation ◽  
High Level ◽  
Year 2000 ◽  
Selection Of

In the year 2000, the Japanese geological disposal program for high-level radioactive waste (HLW) moved from the phase of generic research and development into the phase of implementation. Following legislation entitled the “Specified Radioactive Waste Final Disposal Act” (hereafter “the Act”), the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization in October 2000. The assigned activities of NUMO include repository site selection, developing relevant license applications and construction, operation and closure of the repository. To initiate the first stage, NUMO has chosen an “open solicitation” approach for finding candidate sites in the belief that the support of local communities is essential to the success of this highly public, long-term project extending over more than a century. Based on this concept, NUMO announced the start of open solication for volunteer municipalities for selection of Preliminary Investigation Areas to the public on December 19, 2002. This paper describes NUMO’s open solicitation of volunteer municipalities for a potential disposal site.

scholarly journals Assessing the efficiency of a “buried wall” barrier in the establishment of near-surface long-term storage and disposal facilities for RW

2021 ◽  
Vol 14 (1) ◽  
pp. 96-105
Author(s):  
V. V. Suskin ◽  
◽  
I. V. Kapyrin ◽  
F. V. Grigorev ◽  
◽  
...  
Keyword(s):  
Near Surface ◽  
Transfer Processes ◽  
Long Term Storage ◽  
Mass Transfer Processes ◽  
High Degree ◽  
The Impact ◽  
Term Storage

The article evaluates the impact of a “buried wall” barrier on the long-term safety during the long-term storage1 or in-situ disposal of nuclear legacy facilities, in particular, industrial reservoirs, as well as during the development of near-surface disposal facilities for radioactive waste (RWDF). For assessment purposes, filtration and mass transfer processes have been numerically modelled in the GeRa code based on a case study of a reference near-surface facility. The study explores in which way the available covering screen affects the dynamics of contaminant spread. It evaluates the sensitivity of the results to the dispersion parameter commonly characterized by a high degree of uncertainty.

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