The development of radioactive waste repositories involves consideration of how the waste and the
engineered barrier systems will evolve, as well as the interactions between these and, often relatively
complex, natural systems. The timescales that must be considered are much longer than the timescales
that can be studied in the laboratory or during site characterisation. These and other factors can lead to
various types of uncertainty (on scenarios, models and parameters) in the assessment of long-term,

This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup.

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.

This work was performed to suggest possible strategies for geoscientific classifications in the siting process of a high-level repository. To develop a feasible method for geoscientific classifications, a number of factors of a philosophical character, related to the purpose of the classifications, need to be accounted for. Many different approaches can be visualized, and this report was not intended to present a complete classification methodology.

EPA held a 90-day public comment period for the proposed radiation protection standards for Yucca Mountain (August 27, 1999 through November 26, 1999). Sixty-nine (69) sets of written comments were submitted to EPAÕs Air Docket regarding the proposed standards, although some commenters submitted more than one set of written comments. In addition, the Agency received oral testimony on the proposed standards from 28 speakers during public hearings that were held in Washington, DC; Las Vegas, NV; Amargosa Valley, NV; and Kansas City, MO.

We, the Environmental Protection Agency (EPA), are promulgating public health and safety standards for radioactive material stored or disposed of in the potential repository at Yucca Mountain, Nevada. Section 801 of the Energy Policy Act of 1992 (EnPA, Pub. L. 102Ð486) directs us to develop these standards. Section 801 of the EnPA also requires us to contract with the National Academy of Sciences (NAS) to conduct a study to provide findings and recommendations on reasonable standards for protection of the public health and safety.

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 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.

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.