Questions and Answers to the National Report of the Czech Republic
Questions and Answers to the National Report of the Czech Republic
Questions and Answers to the National Report of the Czech Republic
Questions and Answers to the National Report of the Czech Republic
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
Questions and Answers to the National Report of the Czech Republic
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.
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.
The 9th OECD Nuclear Energy Agency "Forum on Stakeholder Confidence" Community Visit and
National Workshop was held in Karlovy Vary, Chyše and Blatno in the Czech Republic in October 2012.
Entitled "Deliberating Together on Geological Repository Siting", the workshop focussed on the process
for siting an installation for the final management of spent nuclear fuel, and the expectations and
challenges raised by this process. Three themes were examined: developing confidence in a participatory
During the 1990s, nuclear waste programmes in nearly every concerned country met many difficulties. Nuclear waste management was seen as a technical issue, and the local communities were only involved in the last stage of the decision-making process when almost all components of the decision were already fixed. The management of high level radioactive waste is now recognised as a complex decision-making process entailing technical, ethical, social, political and economic dimensions where no solution can be reached solely on the basis of technical considerations.
This report aims to clarify the dynamics of socio-technical challenges in the implementation of geological disposal (GD) for High Level Waste (HLW) and Spent Nuclear Fuel (SNF). Drawing on the 14 country reports produced within InSOTEC’s WP1 the synthesis focuses on socio-technical challenges that appear across national contexts. The synthesis report elucidates issues made visible through bringing together the analyses of different national contexts.
These proposed guidelines are recommendations that have emerged from the European Union Research Project ARGONA (Arenas for Risk Governance), Contract no.: FP6-036413
RD&D Programme 2010 presents SKB’s plans for research, development and demonstration during<br/>the period 2011–2016. SKB’s activities are divided into two main areas: the programme for low- and<br/>intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme.
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.
This report is the National Report submitted by the Czech Republic for the purposes of assessment meeting of the parties to the Joint Convention. Its objective is to describe the fulfillment status of obligations under the Joint Convention in the Czech Republic as on 31 December 2002. The outline of the National Report is based on recommendations approved at the preparatory meeting of the parties to the Joint Convention in December 2001 and contained in the „Guidelines regarding the form and structure of national reports (JC-SFRW/PREP/FINAL/DOCUMENT 3)“ of 13 December 2001.
With the establishment of the “Arbeitskreis Auswahlverfahren Endlagerstandorte” (AkEnd) – the Committee on a Site Selection Procedure for Repository Sites, in the following referred as to as the “committee” - the Federal Minister for the Environment set up a discussion forum on radioactive waste disposal, which has been called for by the public for quite some time.
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 "performance"<br/>refers to the geosphere'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 '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 "alternative design" and "alternative barriers". 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.
This report describes the history, recent developments and the current situation of the management of highly radioactive waste and spent nuclear fuel in the Czech Republic, with a particular focus on the development of geological disposal for this kind of waste. Special attention is given to the interplay of social and technical aspects of the process. The first chapter gives an overview of the state of affairs and sketches out the trajectories leading to it.