scholarly journals Alternative Disposal Options for High-Level Radioactive Waste

2021 ◽  
Vol 1 ◽  
pp. 259-260
Author(s):  
Matthias Englert ◽  
Simone Mohr ◽  
Saleem Chaudry ◽  
Stephan Kurth
Keyword(s):  
Radioactive Waste ◽  
Federal Government ◽  
Nuclear Waste ◽  
Site Selection ◽  
State Of The Art ◽  
Final Disposal ◽  
High Level Radioactive Waste ◽  
Disposal Options ◽  
Deep Boreholes ◽  
High Level

Abstract. Are alternatives to the disposal of high-level radioactive waste in a geology repository conceivable? We present the results of the first phase of a research project on the state of the art in science and technology for alternative disposal options. The project is financed by the Federal Office for the Safety of Nuclear Waste Management. Most recently, in 2015, the German Commission on the Storage of High-Level Radioactive Waste (Endlagerkommission) evaluated possible disposal technologies and classified them as either promising, conceivable, or to be pursued further. Only final disposal in a geological repository was considered promising. Conceivable, but not immediately available or not advantageous, were storage in deep boreholes (DBs), long-term interim storage (LTIS), and partitioning and transmutation (P&T). All other alternative disposal options by burial, dilution, or removal from the planet were determined not to be worth pursuing. The Disposal Commission did conclude that none of the three conceivable methods (DBs, LTIS, P&T) would result in earlier disposal of high-level radioactive waste than the preferred final disposal in a mine. However, it recommended continued tracking and regular monitoring of the future development of alternative disposal options, e.g., disposal in deep boreholes. Finally, in 2017, with the amended Site Selection Act, the federal government specified disposal in a repository mine with the option of retrieval during operation or recovery for 500 years after closure. In a learning site selection process, the Federal Office for the Safety of Nuclear Waste Disposal (BASE) reviews the proposals of the project managing company, the Federal Company for Radioactive Waste Disposal (BGE), and prepares a reasoned recommendation to the federal government for a site with the best possible safety. Part of the reasoned recommendation is, among other things, a discussion of alternative disposal options to final disposal in deep geological formations. In the presentation, we report on the status of international research on alternative disposal options, discuss advantages and disadvantages of the technologies, and evaluate the potential of the technologies for the disposal of high-level radioactive waste in Germany. The LTIS is designed as dry storage in a building to be constructed above ground or near the surface and is expected to last for a period of several hundred years. With LTIS it would be possible to gain time for the development of a suitable final disposal option; however, this also postpones the disposal issue indefinitely into the future with undetermined methods. DB storage would involve sinking the storage containers into boreholes with depths of up to 5000 m. This could reduce the expense and be particularly advantageous for smaller inventories, although the potential for the use of engineered barriers would be limited and retrievability precluded according to the current state of the art in science and technology. P&T is primarily intended to separate long-lived transuranic elements from high-level radioactive waste and then convert them to short-lived fission products by neutron irradiation in reactors. The main goal is to reduce the necessary containment times in the repository by changing the inventory, but the effort to treat the waste would be significant and a repository for high-level nuclear waste is still needed. More exotic ideas for alternative disposal include deep geological injection of liquid waste, waste forms that melt themselves into rock, storage inside the ocean floor or subduction zones, shipment to space, burial in ice sheets, or dilution in the atmosphere and oceans. None of these exotic options is currently being actively pursued.

scholarly journals Status of Deep Borehole Disposal of High-Level Radioactive Waste in Germany

Energies ◽  
2019 ◽  
Vol 12 (13) ◽  
pp. 2580 ◽  
Author(s):  
Guido Bracke ◽  
Wolfram Kudla ◽  
Tino Rosenzweig
Keyword(s):  
Radioactive Waste ◽  
Site Selection ◽  
Real Option ◽  
Selection Process ◽  
Technical Equipment ◽  
Deep Borehole ◽  
Final Disposal ◽  
High Level Radioactive Waste ◽  
High Level ◽  
A Site

The phase-out of nuclear energy in Germany will take place in 2022. A site for final disposal of high-level radioactive waste (HLRW) has not yet been chosen, but a site selection process was restarted by the Site Selection Act in 2017. This Act was based on a recommendation by a commission which also advised to follow up the development of deep borehole disposal (DBD) as a possible option for final disposal of HLRW. This paper describes briefly the status of DBD in Germany and if this option is to be pursued in Germany. Although DBD has some merits, it can only be a real option if supported by research and development. The technical equipment for larger boreholes of the required size will only be developed if there is funding and a feasibility test. Furthermore, any DBD concept must be detailed further, and some requirements of the Act must be reconsidered. Therefore, the support of DBD will likely remain at a low level if there are no political changes.

scholarly journals On the temperature in a final disposal site for high-level radioactive waste

2021 ◽  
Vol 1 ◽  
pp. 99-100
Author(s):  
Ute Maurer-Rurack ◽  
Guido Bracke ◽  
Eva Hartwig-Thurat ◽  
Artur Meleshyn ◽  
Torben Weyand
Keyword(s):  
Radioactive Waste ◽  
Outer Surface ◽  
Site Selection ◽  
Temperature Limit ◽  
Disposal Site ◽  
Final Disposal ◽  
High Level Radioactive Waste ◽  
High Level ◽  
Host Rocks ◽  
Respective Host

Abstract. The Site Selection Act stipulates a precautionary temperature limit of 100 ∘C on the outer surface of the containers with high-level radioactive waste (HLRW) in the final disposal site. This precautionary temperature limit should be applied in preliminary safety analyses provided that the maximum physically possible temperatures in the respective host rocks have not yet been determined due to pending research. Increasing temperatures in the deep geological underground, caused by the heat generation of the HLRW, can trigger thermal, hydraulic, mechanical, chemical and biological processes (THMCB) in the respective host rocks of a final disposal site and thus endanger safety. Furthermore, high temperatures may hamper the feasibility to retrieve and recover HLRW from a final disposal site. Such processes are described in detail in databases for features, events and processes (FEP) databases. Single components or barriers of a final disposal facility may require specific design temperatures for the preservation of their features once a concept for long-term safety of a final disposal site is established; however, the interactions of all relevant processes of a concept for a final disposal site must be considered when a specific temperature limit for the outer surface of the containers is derived. This temperature limit may vary for particular safety and final disposal concepts in the host rock: salt, clay and crystalline rock. The conclusion is that temperature limits regarding the outer surface of the containers should be derived specifically for each safety and disposal concept and should be supported by a solid safety analysis. Temperature limits without reference to specific safety concepts or the particular design of the final disposal site likely narrow down the possibilities for optimisation and could adversely affect the site selection process in finding the best suitable site.

scholarly journals Management of high-level radioactive waste in Germany: roads from storage towards disposal – need and options for action

2021 ◽  
Vol 1 ◽  
pp. 217-218
Author(s):  
Saleem Chaudry ◽  
Angelika Spieth-Achtnich ◽  
Wilhelm Bollingerfehr
Keyword(s):  
Radioactive Waste ◽  
Site Selection ◽  
Selection Process ◽  
Research Project ◽  
Final Disposal ◽  
High Level Radioactive Waste ◽  
The Road ◽  
High Level ◽  
Design Options ◽  
Interim Storage

Abstract. The road towards final disposal of high-level radioactive waste (HAW) produced in Germany requires extensive and foresighted management. To date, HAW has been stored in dual-purpose casks inside 15 interim storage facilities. Finally, it is disposed of in a deep geological repository. A site-selection process for this repository, taking into account the whole national territory, started in 2017. The road from interim storage to final disposal is not yet planned in detail: neither temporally nor spatially nor technically. Important parameters are still unknown. The last operating licenses of the existing interim storage facilities, originally built to last for up to 40 years, will end in 2047, and a concept for prolonged interim storage does not exist. The dates for the decision on the repository site and the start of its operation are plagued by uncertainties, as well as the development of safety concepts for different potential host rocks or knowledge on the long-time behavior of disused fuel assemblies during dry interim storage. According to the German site-selection law (Deutscher Bundestag, 2017) the siting decision for the final repository is planned to be made in 2031; Thomauske and Kudla (2016) drew up timelines for the site-selection process to end between 2059 and 2096. The research project WERA – Management of high-level radioactive waste in Germany: Roads from storage towards disposal – addressed these uncertainties through the development of different design options for the four main steps of the German road to disposal and of a variety of scenarios combining these steps, covering a broad range of potential future designs of the road to disposal. These scenarios have been analyzed in detail. Need for technical and political action along the road to final disposal has been identified. Options for action were named, and their preconditions and consequences were listed. The design options and the scenarios derived form the basis of societal discourse on the disposal of high-level radioactive waste. Thus, the research project WERA contributes toward the politically and societally active integration of the different disposal steps (interim storage, receiving storage facility, waste conditioning, and final disposal).

Towards best possible safety - Current regulatory research for the German site selection process for high-level radioactive waste disposal

2020 ◽  
Author(s):  
Axel Liebscher ◽  
Christoph Borkel ◽  
Ute Maurer-Rurack ◽  
Michael Jendras
Keyword(s):  
Radioactive Waste ◽  
Nuclear Waste ◽  
Site Selection ◽  
Selection Process ◽  
Active Faults ◽  
Radioactive Waste Disposal ◽  
High Level Radioactive Waste ◽  
Research Activities ◽  
Methodological Approaches ◽  
High Level

<p>The German Site Selection Act (Standortauswahlgesetz – StandAG) defines the search for and selection of the national German site with best possible safety for a disposal facility for high-level radioactive waste. The Federal Office for the Safety of Nuclear Waste Management (BASE) is the federal regulatory authority for radioactive waste disposal. BASE supervises the site selection process for a repository for high-level radioactive waste and is responsible for the accompanying public participation. To fulfill its tasks according to the state of science and technology, task related research forms an integral part of BASEs activities. Current research activities in the context of the site selection process address geoscientific questions, methodological aspects of the implementation of the site selection process, and public participation aspects. This contribution provides an overview on the current geoscientific and methodological research activities of BASE.</p><p>According to § 16 StandAG , the national implementer (Bundesgesellschaft für Endlagerung  mbH) has to execute surface-based exploration and BASE has to review and define the respective exploration program. Therefore, the two projects <em>MessEr</em> and <em>übErStand</em> compiled state of science and technology with regard to surface based exploration methods. The foci were on methods suitable for addressing the criteria and requirements set out in the German Site Selection Act.</p><p>The project <em>KaStör</em> reviewed the current knowledge on active faults and fault zones in Germany and studied methodological approaches to date and identify the activity of faulting. The results support BASE to review the application of the exclusion criteria for areas with “active faults zones” according to § 22 (2) StandAG.</p><p>For the time being, § 27 (4) StandAG defines 100 °C as precautionary maximum temperature at the outer surface of waste canisters for all host rocks. The project <em>Grenztemperatur</em> compiled and studied the temperature dependency of the different THMC/B processes according to available FEP catalogues for rock salt, clay stone, and crystalline rock. The project also identified open and pending research questions and describes ways to define host rock specific maximum temperatures based on specific disposal and safety concepts.</p><p>During the site selection process, safety oriented weighting of different criteria and comparison of different potential regions and sites have to be performed. The project <em>MaBeSt</em> studied and reviewed methodological approaches to this weighting and comparison problem with special emphasis on multi criteria analysis (MCA) and multi criteria decision analysis (MCDA).</p><p>Key requirement for safe geological disposal of nuclear waste is barrier integrity. The project <em>PeTroS</em> experimentally studied potential percolation mechanisms of fluids within rock salt at isotropic conditions at disposal relevant pressures and temperatures.</p>

scholarly journals Public opinion in the site selection process: survey methodologies

2021 ◽  
Vol 1 ◽  
pp. 305-306
Author(s):  
Sebastian Götte ◽  
Roman Seidl ◽  
Ariane Breyer ◽  
Zoë Felder
Keyword(s):  
Radioactive Waste ◽  
Site Selection ◽  
Nuclear Energy ◽  
Selection Process ◽  
The Body ◽  
German Population ◽  
Research Association ◽  
Final Disposal ◽  
High Level Radioactive Waste ◽  
High Level

Abstract. The aim of the site selection process (StandAV) is to find the repository site for high-level radioactive waste with the best possible safety. Transparency and public involvement contribute to ensuring that the outcome of the site selection process is “supported by a broad consensus in society and can thus also be tolerated by those affected” (StandAG § 5 para. 1). In order for the public to be suitably informed and involved, BASE (Federal Office for the Safety of Nuclear Waste Management), in particular, as the body responsible for public participation, must base its work on the knowledge, attitudes and needs of the German population. In order to gain the respective knowledge, the company aproxima Gesellschaft für Markt- und Sozialforschung Weimar mbH was commissioned to conduct a repetitive representative survey (research project EWident). The study briefly deals with nuclear energy in general, but mainly focuses on questions related to the topic of final disposal (knowledge of the topic and especially the StandAV, interest in information and involvement, relevance of particular questions in the process, etc.). The first survey took place in summer 2020. A special focus was placed on the younger generation (14- to 29-year-olds). The results can be viewed on the BASE website (Götte and Ludewig, 2020). They show that the level of knowledge about and interest in StandAV are still rather feeble; at the same time, it is clear that questions of safety are a central driver for accepting a possible site in one's own region. A second survey is planned for autumn 2021. A comparably broadly drawn survey has not been carried out in recent years. However, the fact that the topic of final disposal is becoming increasingly important is shown by thematically related surveys that ask about attitudes towards nuclear energy or examine particular aspects of StandAV in more detail. Within the framework of the TRANSENS research association (Transdisciplinary Research on the Management of High-Level Radioactive Waste in Germany), for example, trust and confidence in the context of the site selection process were surveyed. The 60 min workshop is aimed at interested parties and researchers who would like to contribute their own experiences with related surveys. In the workshop we provide three incentives. aproxima introduces the methods and key results of EWident's first survey. BASE gives an insight into the practical use of these results. Roman Seidl of Leibniz University Hannover reports the results of the TRANSENS survey. Subsequently, we would like to discuss the following questions, among others, with the participants in the workshop. What is remarkable about the results? Do they differ from other StandAV surveys and experiences, and if so, how? How can this be explained? What further research needs can be identified? With what approaches could they be met?

Significance of long-term climate evolution and associated impacts on the long-term safety of a high-level radioactive waste repository within the German siting process

2021 ◽  
Author(s):  
Marc Wengler ◽  
Astrid Göbel ◽  
Eva-Maria Hoyer ◽  
Axel Liebscher ◽  
Sönke Reiche ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Site Selection ◽  
Phase 1 ◽  
High Level Radioactive Waste ◽  
Safety Requirements ◽  
Climate Evolution ◽  
Safety Assessments ◽  
High Level ◽  
Host Rocks

<p>According to the 'Act on the Organizational Restructuring in the Field of Radioactive Waste Disposal' the BGE was established in 2016. The amended 'Repository Site Selection Act' (StandAG) came into force in July 2017 and forms the base for the site selection by clearly defining the procedure. According to the StandAG the BGE implements the participative, science-based, transparent, self-questioning and learning procedure with the overarching aim to identify the site for a high-level radioactive waste (HLW) repository in a deep geological formation with best possible safety conditions for a period of one million years.</p><p>The German site selection procedure consists of three phases, of which Phase 1 is divided into two steps. Starting with a blanc map of Germany, the BGE completed Step 1 in September 2020 and identified 90 individual sub-areas that provide favorable geological conditions for the safe disposal of HLW in the legally considered host rocks; rock salt, clay and crystalline rock. Based on the results of Step 1, the on-going Step 2 will narrow down these sub-areas to siting regions for surface exploration within Phase 2 (§ 14 StandAG). Central to the siting process are representative (Phase 1), evolved (Phase 2) and comprehensive (Phase 3) preliminary safety assessments according to § 27 StandAG.</p><p>The ordinances on 'Safety Requirements' and 'Preliminary Safety Assessments' for the disposal of high-level radioactive waste from October 2020 regulate the implementation of the preliminary safety assessments within the different phases of the siting process. Section 2 of the 'Safety Requirements' ordinance provides requirements to evaluate the long-term safety of the repository system; amongst others, it states that all potential effects that may affect the long-term safety of the repository system need to be systematically identified, described and evaluated as “expected” or “divergent” evolutions. Additionally, the ordinance on 'Preliminary Safety Assessments' states in § 7, amongst others, that the geoscientific long-term prediction is a tool to identify and to evaluate geogenic processes and to infer “expected” and “divergent” evolutions from those. Hence, considering the time period of one million years for the safe disposal of the HLW and the legal requirements, it is essential to include long-term climate evolution in the German site selection process to evaluate the impact of various climate-related scenarios on the safety of the whole repository system.</p><p>To better understand and evaluate the influence of climate-related processes on the long-term safety of a HLW repository, climate-related research will be a part of the BGE research agenda. Potential research needs may address i) processes occurring on glacial – interglacial timescales (e.g. the inception of the next glaciation, formation and depth of permafrost, glacial troughs, sub-glacial channels, sea-level rise, orbital forcing) and their future evolutions, ii) effects on the host rocks and the barrier system(s) as well as iii) the uncertainties related to these effects but also to general climate models and predictions.</p>

scholarly journals Section 14 StandAG – Identification of siting regions and associated challenges

2021 ◽  
Vol 1 ◽  
pp. 49-50
Author(s):  
Lisa Seidel ◽  
Marc Wengler
Keyword(s):  
Radioactive Waste ◽  
Phase I ◽  
Site Selection ◽  
Selection Procedure ◽  
Radioactive Waste Disposal ◽  
Second Step ◽  
High Level Radioactive Waste ◽  
Surface Exploration ◽  
Safety Assessments ◽  
High Level

Abstract. With the publication of the subarea interim report on sub-regions on 28 September 2020, the Federal Company for Radioactive Waste Disposal (BGE), as the implementer of the German site selection procedure, has completed the first step of phase I in due time. The second step of phase I is the identification of siting regions for surface exploration. In the following step 2 of phase I, the determination of siting regions for surface exploration will be carried out based on the interim results of the first step of phase I in accordance with section 14 of the regulating law (StandAG). A central component of this second step of phase I is the representative preliminary safety assessments pursuant to section 27 StandAG, the ordinances on “Safety Requirements” (EndlSiAnfV) and “Preliminary Safety Assessments” (EndlSiUntV), which are carried out for each of the sub-regions. Based on the results of the preliminary safety assessments and the renewed application of the geoscientific weighting criteria (section 24 StandAG), siting regions will be identified that have the potential to become the site with the best possible safety for a repository for high-level radioactive waste. During the second step of phase I, the planning scientific consideration criteria (section 25 StandAG) can be applied for the first time. The path to the siting regions for surface exploration can be accompanied by various challenges related to geoscientific, methodological and also societal questions. For example, the application of the representative preliminary safety assessments may be more challenging in larger subareas compared to smaller ones as subsurface properties are likely to be more variable. In this context, areas with little data coverage for example, and the treatment of these areas in the procedure may pose another challenge. Therefore, sound methodological concepts must be developed for performing the representative preliminary safety assessments as well as for applying the geoscientific weighting criteria. Furthermore, the German site selection procedure defines special requirements (section 1 StandAG): the implementation of the participatory, science-based, transparent, self-questioning and learning procedure poses challenges to all stakeholders of the procedure on the way to the best possible disposal of high-level radioactive waste.

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