This report is issued according to Article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management.<br/>Sweden signed the Joint Convention September 29, 1997, the first day it was open for signing, during the ongoing General Conference at IAEA.

Local support in favor of a final repository for spent nuclear in one's own municipality has increased somewhat in both Oskarshamn and Östhammar. This is shown by the annual public opinion poll that was conducted by Synovate on behalf of SKB.

Summary of radioactive waste and management programs in Sweden, including national nuclear energy context; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; authorities and implementing organizations; financing; and public information.

Web page from SKB's website (Swedish Nuclear Fuel and Waste Management Company), announcing that it has selected Forsmark, in the municipality of Östhammar, as the site for the final repository for Sweden's spent nuclear fuel.

Web page from SKB's website (Swedish Nuclear Fuel and Waste Management Company) discussing the ongoing cooperation between SKB and both Östhammar, where the repository is to be sited, and Oskarshamn, where the encapsulation plant is to be located.

Long-term radioactive waste management (RWM) involves large and long-term research and development programmes in essentially all countries with civil nuclear programmes. Such programmes develop through different phases from basic research to more focussed applied research and development (R&D) and finally to the design and siting of proposed solutions. Internationally basic principles for the conduct of these programmes, basic safety principles and guidance on how to comply with them have largely been agreed upon.

The 1976 Parliamentary election in Sweden resulted in a coalition government which imposed extremely stringent requirements for the waste produced by Swedish nuclear power plants. The industry responded with a crash study, the Nuclear Fuel Safety (KBS) project, with experts drawn from hundreds of universities and related scientific institutions. A year later, the industry presented “a complete scheme for absolutely safe storage of nuclear waste” in engineered facilities located at about 500 m depth in the Swedish granite bedrock (KBS-I).

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.

Spent fuel in Sweden emanates mainly from four commercial nuclear power plants, one material testing<br/>reactor and one research reactor. The radioactive waste originates from the nuclear power industry as well<br/>as medical use, industry, research and consumer products.

The concept of Geosphere Perfonnance Indices (GPis) is proposed. The &quot;performance&quot;<br/>refers to the geosphere&#39;s capacity to retain/contain radionuclides in the event of their accidental<br/>release at some point in time. The GPis are based on the Lagrangian stochastic-analytical<br/>framework for transport in the subsurface and are believed to render useful tools in performance<br/>assessment studies in general and in the site selection process in particular.

RD&D Programme 2007 presents SKB’s plans for research, development and demonstration during<br/>the period 2008–2013. The plans for the first three-year period are for natural reasons more detailed<br/>than those for the next one.

In an international perspective, Sweden has come a long way in the development of safe and accepted systems for the management and disposal of radioactive waste. <br/><br/>A complete system for sea transport of spent nuclear fuel from the twelve Swedish nuclear reactors has been in operation since 1982. The spent nuclear fuel will be stored in CLAB for a period of about 40 years up until final disposal. The facility has been in operation since 1985. A final repository for low- and intermediate-level short-lived waste, SFR, has been in operation since April 1988.

The preceding RD&D-Programme from 2001 was concentrated on research and technology development. Research with a focus on the assessment of long-term safety was emphasized and viewpoints from previous reviews of SR 97 and RD&D-Programme 98 were dealt with in depth. SR 97 was an assessment of the long-term safety of a deep repository for spent nuclear fuel. This RD&D-Programme 2004 focuses its attention on the development of technologies for fabrication and sealing of canisters for final disposal of spent fuel.

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 &#39;s activities relating to the siting of a deep geological<br/>repository.

The goal of radioactive waste management in Sweden is to dispose of all radioactive waste products generated at the Swedish nuclear power plants in a safe manner. Furthermore, all other radioactive waste that arises in Sweden shall be safely disposed of.<br/>The Act on Nuclear Activities requires that the owners of the Swedish nuclear power plants adopt the measures that are needed to achieve this goal. The owners of the Swedish nuclear power plants have commissioned the Swedish Nuclear Fuel and Waste Management Company (SKB) to implement the measures that are needed.<br/>

This report is a background to RD&D-Programme 98 /1-11. The report gives an account of most of the research and development being conducted by SKB. The current state of knowledge is described, along with the goals and programmes that govern the continued work. The period of immediate concern comprises the next three years, 1999-2001. Particulars for the three years following that are for natural reasons less detailed and mainly indicate a direction.

The present report discusses the implications of the terms &quot;alternative design&quot; and &quot;alternative barriers&quot;. Furthermore, different schematic methods for final disposal and different components that can be included in a system for final disposal are presented. The ideas for the different methods, components or designs come from many sources.

The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19,1989 in Washington, D.C.