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Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 6 - App 1
Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 6 - App 1
In RD&D-Programme 92, SKB presented a partially new strategy for its activities. The new strategy entailed a focusing and concentration on the implementation of deep disposal of a limited quantity (about 800 tonnes) of encapsulated spent nuclear fuel during the coming 20-year period. Following this initial deposition, the results of the work will be evaluated, and only then will a decision be taken as to how and when regular deposition of the main body of the fuel and other long-lived nuclear waste will take place.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Finland signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The major generators of radioactive waste in Finland are the two nuclear power plants, the Loviisa and Olkiluoto plants. The Loviisa plant has two PWR units, operated by Fortum Power and Heat Oy, and the Olkiluoto plant two BWR units, operated by Teollisuuden Voima Oy.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 4th Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 4th Finnish National Report as referred to in Article 32 of the Convention
This is the Finnish National Report, in accordance with the provisions of the Article 32 of the Joint Convention, to the 4th Review Meeting of the Contracting Parties in May 2012. The aim of this report is to present the recent developments of waste management in Finland, to describe waste management facilities and practices in Finland and, for discussion and review among contracting parties, to describe how the obligations under the Convention are fulfilled in Finland.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 29 September 1997 in the Vienna Diplomatic Conference. Finland signed the Convention on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The fulfillment of the obligations of the Convention and the developments after the second Review Meeting are assessed in this report.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Hastholmen Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Hastholmen Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Hastholment.
Handling and final disposal of nuclear waste: Siting of a deep repository
Handling and final disposal of nuclear waste: Siting of a deep repository
The siting of the facilities for the disposal of spent nuclear fuel and other long-lived<br/>nuclear waste is one of the central remaining tasks within the Swedish waste programme.<br/>Work relating to the siting of the repository is being conducted in stages and will<br/>continue for most of the 1990:ies. This report describes the background to, the goals<br/>for and structure of SKB 's activities relating to the siting of a deep geological<br/>repository.
Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management
Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management
This report analyses mediation and mediators in Swedish nuclear waste management. Mediation is about establishing agreement and building common knowledge. It is argued that demonstrations and dialogue are the two prominent approaches to mediation in Swedish nuclear waste management. Mediation through demonstration is about showing, displaying, and pointing out a path to safe disposal for inspection. It implies a strict division between demonstrator and audience.
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Safety Case Plan
Safety Case Plan
Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy) Posiva is preparing to submit the construction license application for a spent fuel repository by the end of the year 2012. The long-term safety section supporting the license application is based on a safety case, which, according to the internationally adopted definition, is a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository.
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Olkiluoto Site Description
Olkiluoto Site Description
This second version of the Olkiluoto Site Report, produced by the OMTF (Olkiluoto Modelling Task Force), updates the Olkiluoto Site Report 2004 (Posiva 2005) with the data and knowledge obtained up to December 2005.<br/>The main product of the modelling has been to develop a descriptive model of the site (the Site Descriptive Model), i.e. a model describing the geometry, properties of the bedrock and the water and the associated interacting processes and mechanisms.
Expert Judgement in Performance Assessment
Expert Judgement in Performance Assessment
Proposals to site, construct and operate a radioactive waste disposal facility in Sweden will be supported by performance assessments (PAs). Such PAs will require a range of expert judgements to be made. As part of SKI’s preparation for reviewing SKB’s Pas and for conducting independent PAs, SKI has identified a need for further research on the treatment of expert judgement in PA.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Kivetty.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Romuvaara Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Romuvaara Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Romuvaara.
Interim Summary Report of the Safety Case
Interim Summary Report of the Safety Case
The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository
Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 1 - 5
Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 1 - 5
In RD&D-Programme 92, SKB presented a partially new strategy for its activities. The new strategy entailed a focusing and concentration on the implementation of deep disposal of a limited quantity (about 800 tonnes) of encapsulated spent nuclear fuel during the coming 20-year period. Following this initial deposition, the results of the work will be evaluated, and only then will a decision be taken as to how and when regular deposition of the main body of the fuel and other long-lived nuclear waste will take place.
Site selection - Siting of the Final Repository for Spent Nuclear Fuel
Site selection - Siting of the Final Repository for Spent Nuclear Fuel
SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection<br/>is the end result of an extensive siting process that began in the early 1990s. The strategy and<br/>plan for the work was based on experience from investigations and development work over a period<br/>of more than ten years prior to then.<br/>This document describes the siting work and SKB’s choice of site for the final repository.
Handling and final disposal of nuclear waste. September 1989
Handling and final disposal of nuclear waste. September 1989
For those parts of the waste system that have already been taken into operation - transportation and handling systems, central interim storage facility for spent nuclear fuel (CLAB) and final repository for reactor waste (SFR)- the research and development stage has already largely been passed. The programme presented here therefore pertains primarily to the treatment and final disposal of spent fuel and the decommissioning of nuclear power plants.
Handling and final disposal of nuclear waste. September 1986
Handling and final disposal of nuclear waste. September 1986
The Act on Nuclear Activities (SFS 1984:3) obligates the owners of the Swedish nuclear power plants to<br/>jointly prepare a comprehensive programme for the research and development work and other measures<br/>required for the safe management and disposal of the waste from nuclear power.<br/>For those parts of the waste system that have already been taken into operation or are under construction - transportation and handling systems, central interim storage facility for spent nuclear fuel (CLAB) and final repository for reactor waste (SFR) - the research and development st
The Final Disposal Facility for Spent Nuclear Fuel
The Final Disposal Facility for Spent Nuclear Fuel
Thorough long-term studies have shown that the Finnish bedrock is suitable for the permanent isolation of spent nuclear fuel from organic nature. Legislation requires that besides safety, an assessment be made of any other environmental impacts of the final disposal facility. Environmental impact assessment (EIA) in respect of the final disposal facility for spent nuclear fuel got under way in 1997 when Posiva Oy, which is responsible for the project, began work on an EIA programme.
Posiva Annual Report
Posiva Annual Report
Main events Licensing process proceeds according to plan Posiva aims to submit the construction license application in 2012. In 2011, research and analysis work continued to ensure the timely availability of results and related reports. The feedback provided by the Radiation and Nuclear Safety Authority and other authorities for the preliminary licensing documentation submitted in 2009 was systematically reviewed in 2011, and steps were taken to ensure it is taken into account during the license submission phase.
From Risk Analysis to the Safety Case. Values in Risk Assessments
From Risk Analysis to the Safety Case. Values in Risk Assessments
The foundation for work related to nuclear waste management is laid by laws and outlines e.g. the responsibilities of the reactor owners and the state, as represented by the authorities. The Swedish Nuclear Fuel and Waste Management Company (SKB), as well as Posiva Oy in Finland, were set up by the reactor owners in the respective countries in response to the responsibilities of planning, conducting research and to implement the physical structures leading to a safe management of nuclear wastes.
Structure for Transparency in Nuclear Waste Management
Structure for Transparency in Nuclear Waste Management
The purpose of this report is a comparison of the structures for nuclear waste management in France, Sweden and UK. The source materials for this comparison are studies carried out in each of these countries by Syncho Ltd. over the past 5 years. The Swedish structural review was sponsored by SKI and SSI, and carried out as a pilot study during the years 1996 and 1997 (Espejo & Gill, 1998) as part of the RISCOM I project.