Euradwaste '08 - EU Bookshop - Europa
Euradwaste '08 - EU Bookshop - Europa Euradwaste '08 - EU Bookshop - Europa
According to a clearly-defined and demonstrable physical approach to quality, the reliability of the safety assessment of a long-term repository relies on our capability to describe the different phenomena occurring over time. In certain cases, those phenomena may be coupled, as in the case of expectable thermomechanical effects after the emplacement of highly-exothermal packages. As for processes likely to occur over the very long term (i.e., mostly chemical processes and radionuclide migration), a sound physical control reduces the propagation of uncertainties relating to an insufficient description or model. The required parameters to describe that process must also be known with an appropriate level of precision, and the associated uncertainties must be submitted to essential sensitivity tests in order to ensure that the repository meets its operational and performance targets. In order to provide a sound description of the repository’s determining phenomena, I would like to point out the methodology developed and implemented by Andra, which consists of a phenomenological analysis of repository situations and a description of the phenomena tracking down the evolution of the repository at each space and time field. From the previous example, we may retain the thermal effects relating to the presence of exothermal packages that will need to be taken into account throughout the heat-release period of the packages. In the case of vitrified waste, heat releases decrease after a few centuries and cease to determine the behaviour of disposal structures over time. Inversely, any phenomenon involving radionuclide migration may only be taken into account once waste containers are corroded. That type of extremely rigorous and systematic analysis conducted over the entire repository avoids excessive couplings between the thermal, mechanical, hydraulic and chemical characteristics of the repository, which are not always necessarily described properly. The reader may refer to Andra’s Dossier 2005 for complementary information on the selected approach for the phenomenological analysis of repository situations and a sound perspective view of the phenomena in relation to the space and time dimensions to be taken into account [4]. Keeping in line with the demonstration capability and, consequently, with the confidence that our researchers may have in their models, the goal will be to seek the simplest designs possible. The purpose is not only to describe and model easy geometries, but also to favour certain operating conditions. With reference once again to the Callovo-Oxfordian argillites mentioned in the Dossier 2005, the temperature is limited to 90°C on the walls of disposal structures, with a view to staying within a describable operating field without having to go through more complex diphasic behaviours. By opting for simplicity, not only does modelling become easier, but the demonstration as well. However, some inevitable fields of physics remain pending and insufficiently described, as in the case of gas production and behaviour throughout the lifetime of the repository. All organisations in charge of 0-waste management have agreed to raise the issue among the priorities for the 7 th Framework Project for Research and Development (FPRD), and the FORGE Project should provide responses to fulfil the ambitions of the safety demonstration for waste repositories. Physical modelling is therefore a determining factor. However, we are confronted with space and time scales that are way above the field of experience. All investigations conducted in many surface laboratories and all experiments carried out in underground laboratories will only cover several decades at best, whereas safety demonstrations extend over timescales that are much longer by three to five orders of magnitude. It is therefore necessary to deepen the analysis over several tens or hundreds of millennia. Once again, the quality of the analysis will rely on the quality of the simulation means and of the digital approaches. Qualified methods must be available in order to change both space and time scales efficiently, to analyse the impact of parameter uncertainties and to study the nature of the various effects throughout the lifetime of the repository. Generally speaking, it will be possible to analyse the impact of a leaking package or of a borehole intrusion within the repository. Today, thanks to the growing efforts in modelling and in digital simulations for more than 10 years, we may considerer the “black-box era” to be obsolete and welcome rather increasingly clear and convincing descriptions. The numerous projects supported by the EC will have 36
contributed to enhance knowledge about processes and phenomena, such as the mechanisms regulating the chemical composition of deep waters (ARCHIMEDE Project), to reduce uncertainties on data (CHEMVAL Project on thermodynamic data and the NEA Thermochemical Database Project), to carry out an intercomparison of modelling approaches (DECOVALEX for hydromechanical couplings). More recently, the Projects on the Near-Field Phenomena (NF-PRO), on Fundamental Processes of Radionuclide Migration (FUNMIG) and on Performance Assessment Methodologies in Application to Guide the Development of the Safety Case (PAMINA) made it possible in the framework of the 6 th FPRD to reassess our current knowledge, to generate stabilised data and to propose integration modalities for those data in the safety assessments. 5. Major technological challenges From the technological standpoint, the major challenges consist in being able to take into account simultaneously nuclear-safety requirements during the operating stage and the constraints of the mining environment. Agencies have already achieved decisive advances in the field with the emergence of the first industrial complexes. The most remarkable achievement so far is undoubtedly the encapsulation plant for which the Swedish Nuclear Fuel and Waste Management Company (SKB) has submitted an application in 2008 with a view to using that copper friction-welding process. During the 6 th FPRD, significant efforts were made throughout Europe in the framework of the Project on Engineering Studies and Demonstration of Repository Designs (ESDRED) led by Andra. Several handling demonstrators for waste packages were built, including an emplacement robot for vitrified waste packages in horizontal cavities (Figure 4), as well as the moving of charges up to 80 t for the horizontal transfer of spent-fuel packages. Those demonstrators are on display at the Technological Centre, in Saudron, which is located very close to the Meuse/Haute-Marne Underground Research Laboratory, on the outskirts of Bure. Figure 4: General layout for the horizontal emplacement of a waste canister There are still many development and implementation needs to fulfil, especially in order to carry out operations with automated and often-sophisticated devices in order to minimise human interventions and, hence, ensure maximum safety to the operating staff. With regard to design and construction, several options remain open for the different projects, notably for the choice of access to underground installations, either down a ramp or vertical shafts. The overall arguments are analysed in relation to their specific environments and limitations in order to make timely choices. Requirements are also becoming clearer concerning the phase following the emplacement of disposal packages in underground cavities. The first challenge is the reversibility of the repository and the retrievability of the waste packages. That issue is particularly important in France and is being addressed by various activities at the international scale. Following the preliminary reflections made in the late 1990s and the European project on that topic, a new step was launched by an NEA 37
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- Page 20 and 21: Ms Monika Hammarström of SKB in Sw
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- Page 26 and 27: Dr Peter Blümling of Nagra in Swit
- Page 28 and 29: Future directions There seemed to b
- Page 31 and 32: 1. Introduction Keynote Address Pet
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- Page 43: General introduction and objectives
- Page 47 and 48: Radioactive waste management: Where
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- Page 57 and 58: PANEL DISCUSSION Summary of the Pan
- Page 59: With the support of IAEA preliminar
- Page 63 and 64: Assessment of Financial Provisions
- Page 65 and 66: collected in the cost of the nuclea
- Page 67 and 68: erated by Fortum) and one PWR unit
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According to a clearly-defined and demonstrable physical approach to quality, the reliability of the<br />
safety assessment of a long-term repository relies on our capability to describe the different phenomena<br />
occurring over time. In certain cases, those phenomena may be coupled, as in the case of<br />
expectable thermomechanical effects after the emplacement of highly-exothermal packages. As for<br />
processes likely to occur over the very long term (i.e., mostly chemical processes and radionuclide<br />
migration), a sound physical control reduces the propagation of uncertainties relating to an insufficient<br />
description or model. The required parameters to describe that process must also be known<br />
with an appropriate level of precision, and the associated uncertainties must be submitted to essential<br />
sensitivity tests in order to ensure that the repository meets its operational and performance targets.<br />
In order to provide a sound description of the repository’s determining phenomena, I would<br />
like to point out the methodology developed and implemented by Andra, which consists of a phenomenological<br />
analysis of repository situations and a description of the phenomena tracking down<br />
the evolution of the repository at each space and time field. From the previous example, we may<br />
retain the thermal effects relating to the presence of exothermal packages that will need to be taken<br />
into account throughout the heat-release period of the packages. In the case of vitrified waste, heat<br />
releases decrease after a few centuries and cease to determine the behaviour of disposal structures<br />
over time. Inversely, any phenomenon involving radionuclide migration may only be taken into<br />
account once waste containers are corroded. That type of extremely rigorous and systematic analysis<br />
conducted over the entire repository avoids excessive couplings between the thermal, mechanical,<br />
hydraulic and chemical characteristics of the repository, which are not always necessarily described<br />
properly. The reader may refer to Andra’s Dossier 2005 for complementary information on<br />
the selected approach for the phenomenological analysis of repository situations and a sound perspective<br />
view of the phenomena in relation to the space and time dimensions to be taken into account<br />
[4].<br />
Keeping in line with the demonstration capability and, consequently, with the confidence that our<br />
researchers may have in their models, the goal will be to seek the simplest designs possible. The<br />
purpose is not only to describe and model easy geometries, but also to favour certain operating conditions.<br />
With reference once again to the Callovo-Oxfordian argillites mentioned in the Dossier<br />
2005, the temperature is limited to 90°C on the walls of disposal structures, with a view to staying<br />
within a describable operating field without having to go through more complex diphasic behaviours.<br />
By opting for simplicity, not only does modelling become easier, but the demonstration as<br />
well.<br />
However, some inevitable fields of physics remain pending and insufficiently described, as in the<br />
case of gas production and behaviour throughout the lifetime of the repository. All organisations in<br />
charge of 0-waste management have agreed to raise the issue among the priorities for the<br />
7 th Framework Project for Research and Development (FPRD), and the FORGE Project should provide<br />
responses to fulfil the ambitions of the safety demonstration for waste repositories.<br />
Physical modelling is therefore a determining factor. However, we are confronted with space and<br />
time scales that are way above the field of experience. All investigations conducted in many surface<br />
laboratories and all experiments carried out in underground laboratories will only cover several<br />
decades at best, whereas safety demonstrations extend over timescales that are much longer by<br />
three to five orders of magnitude. It is therefore necessary to deepen the analysis over several tens<br />
or hundreds of millennia. Once again, the quality of the analysis will rely on the quality of the<br />
simulation means and of the digital approaches. Qualified methods must be available in order to<br />
change both space and time scales efficiently, to analyse the impact of parameter uncertainties and<br />
to study the nature of the various effects throughout the lifetime of the repository. Generally speaking,<br />
it will be possible to analyse the impact of a leaking package or of a borehole intrusion within<br />
the repository. Today, thanks to the growing efforts in modelling and in digital simulations for<br />
more than 10 years, we may considerer the “black-box era” to be obsolete and welcome rather increasingly<br />
clear and convincing descriptions. The numerous projects supported by the EC will have<br />
36