The Federal Government will continue to meet Germany’s existing international obligations, particularly with regard to fulfilment of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. In submitting this report, Germany is demonstrating its compliance with the Joint Convention and how it ensures the safe operation of facilities for the management of spent fuel and radioactive waste, including the decommissioning of nu-clear installations.

The European Atomic Energy Community (“Euratom”) is a regional organisation, as referred to in Article 39(4) of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. It became a party to the Convention on 2 January 2006. This report is submitted in compliance with Articles 30 and 32 of the Convention for the Second Review Meeting of the Contracting Parties, to be held in Vienna from 15 to 26 May 2006.

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

The Federal Government will continue to meet Germany’s existing international obligations, par- ticularly with regard to fulfilment of the Joint Convention. In submitting this report, the Federal Re- public of Germany is demonstrating its compliance with the Joint Convention and ensuring the safe operation of facilities for the management of spent fuel and radioactive waste, including the de- commissioning of nuclear installations. At the same time, there is still a need for future action in order to maintain the required high standards of safety and ensure disposal.

News item from NEI summarizing siting process for nuclear waste repositories in Sweden, Finland and France.

There are currently nine power reactors in operation in Germany. These are exclusively light-water reactors (seven pressurised water reactors and two boiling water reactors whose fuel assemblies are composed of low-enriched uranium oxide or uranium/plutonium mixed oxide (MOX)).

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Questions and Comments in 2009 on the National Report posed to Germany

Over the past forty years, the development of the technology needed to isolate radioactive waste in underground rock systems has been found to be a formidable problem. This is especially the case in connection with high-level waste (HLW) after its removal from operations in nuclear power plants. There is also the additional problem of isolating low- and intermediate-level waste (LILW).

The first worldwide review of geological problems in radioactive waste isolation was published by the Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) in 1991 (Witherspoon, 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 9Ð19, 1989, in Washington, D.C.

History shows that the search for sites for radioactive waste management facilities has been marred by conflicts and delays. Affected communities have often objected that their concerns and interests were not addressed. In response, institutions have progressively turned away from the traditional “decide, announce and defend” model, and are learning to “engage, interact and co-operate”. This shift has fostered the emergence of partnerships between the proponent of the facility and the potential host community, as shown in a recent NEA study.

This report was written within the EU-project InSOTEC (www.insotec.eu) which aims to generate a better understanding of the complex interplay between the technical and the social in radioactive waste management and, in particular, in the design and implementation of geological disposal. In a first step 13 countries have been analysed in order to identify prevailing socio-technical challenges.

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.

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.