Japan Atomic Energy Agency (JAEA) Brochure
Japan Atomic Energy Agency (JAEA) Brochure
JAEA Brochure
JAEA Brochure
Nuclear facilities in Japan are as listed in the following table, the details of which are described in Section D.
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.
Radioactive waste is produced from a wide range of human activities. The wastes arising from the nuclear fuel cycle occur as a wide range of materials and in many different physical and chemical forms, contaminated with varying activities of radionuclides. Their common feature is the potential hazard associated with their radioactivity and the need to manage them in such a way as to protect the human environment. The safe disposal of radioactive waste is a key reequirement of the nuclear industry worldwide.
The constraints set by the Japanese HLW disposal programme – particularly associated with
the decision to initiate siting by an open call for volunteers to host a geological repository –
pose particular challenges for repository project management. In order to maintain the
flexibility required to respond to the conditions found at volunteer sites, NUMO has not
published reference designs or site characterisation plans, as is normal for programmes
progressing by site nomination. Instead, we have developed a methodology – the NUMO
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)).
Historically, electricity generated in Switzerland came exclusively from hydropower without any recourse to fossil fuels, the latter not being available as a natural resource in the country. In the mid 1950's, an interest in the relatively new nuclear energy technology was manifested to cover an increasing electricity demand. In accordance with the general policy concerning the production of electricity, the promotion and use of nuclear energy was left to the initiative of the private sector.
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
Nuclear facilities in Japan are listed in Table A1-1, the details of which are described in Section D.<br/>The overview of spent fuel management and radioactive waste management and the current<br/>status of the preparation of radioactive waste disposal regulation system are shown in Table<br/>A1-2 and Table A1-3 respectively.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting - Annexes
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.
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.
The primary objective of government policy, and of NUMO in implementing this policy is to ensure that a repository for Japan’s high-level radioactive waste is designed and located so as to provide secure isolation of the waste and adequate safety for present and future generations. This requires that the site of a repository has to be chosen carefully and an associated repository concept is selected which is appropriate for its specific geological and environmental conditions. At NUMO, we have chosen to implement a volunteering approach to siting.
The report begins with a consideration of the factors which have led to a growth in the use of dialogue processes, a clarification of key concepts and a classification of dialogue processes. A description of recent and current activities in Europe and North America is followed by discussion of the relationship of processes and contexts. This then leads to an identification of the key aims and evaluation criteria which will be used in the design of dialogue processes to be conducted in subsequent phases of the project.