bluuebunny/crossref_metadata_2025_split huggingface dataset:
Numerical assessment of the barrier integrity for a generic nuclear waste repository in crystalline rock
Authors: Guevara Morel Carlos , Maßmann Jobst , Thiedau Jan 
Published: September 2023

Abstract. Since a sufficiently large undisturbed rock zone to provide the essential
safety function for containment of radioactive waste cannot be assumed in
crystalline rock, a concept for disposal in multiple smaller unfractured
rock volumes has been developed and investigated in the joint research
project CHRISTA-II (Thiedau et al., 2021). This repository concept, which relies on the host rock as an essential barrier for the containment of the disposed radionuclides, thus requires the existence of sufficiently large unfractured areas. Integrity evaluation of the geological barrier as part of the safety
assessment comprises a safety-oriented assessment of mechanical, hydraulic,
thermal and chemical processes occurring in the host rock as well as their couplings. Fractures and other types of discontinuities, which usually characterize crystalline rock, are expected to influence the hydraulic behavior of the system. Therefore, representing adequately the fracture network is necessary in order to capture its relevant properties, which will ultimately define the hydraulic boundary conditions surrounding the unfractured containment rock zones. Typically it is only possible to
characterize fracture networks statistically, which requires a systematic
investigation to quantify the influence of multiple realizations on a
repository system. Moreover, the estimation of the potentially available
undisturbed rock zone volume, making use of an ensemble of statically
equivalent fracture networks, is relevant for the repository concept
presented here. This contribution aims to further develop the methodology
for integrity assessment presented in Thiedau et al. (2021) with a focus on the influence of the uncertain fracture distribution.
THEREDA – Thermodynamic Reference Database
Authors: Moog Helge C. , Scharge Tina , Seher Holger , Bok Frank , Brendler Vinzenz , Richter Anke , Wissmeier Laurin , Henneberg Mareike , Altmaier Marcus , Gaona Xavier , Cevirim-Papaioannou Nese , Freyer Daniela , Pannach Melanie , Sohr Julia , Voigt Wolfgang 
Published: September 2023

Abstract. Part of the process to ensure the safety of radioactive
waste disposal is the predictive modeling of the solubility of all relevant
toxic components in a complex aqueous solution. To ensure the reliability of thermodynamic equilibrium modeling and to facilitate the comparison of such calculations done by different institutions, it is necessary to create a mutually accepted thermodynamic reference database. To meet this demand, several institutions in Germany joined efforts and created the Thermodynamic Reference Database (THEREDA; Moog et al., 2015). THEREDA is a suite of programs at the base of which resides a relational
database. Special emphasis is placed on thermodynamic data along with suitable
Pitzer coefficients which allow for the calculation of solubilities in
high-saline solutions. Registered users may either download a single
thermodynamic datum or ready-to-use parameter files for the geochemical
speciation codes PHREEQC, Geochemist's Workbench, CHEMAPP, or TOUGHREACT.
Data can also be downloaded in a generic JSON format to allow for import into other codes. The database can be accessed via the world-wide web: http://www.thereda.de (last access: 13 July 2023). Prior to release, the released part of the database is subjected to many
tests. Results are compared to results from earlier releases and among the
different codes. This is to ensure that, by additions of new and modifications
of existing data, no adverse side-effects on calculations are caused.
Furthermore, our website offers an increasing number of examples for
applications, including graphical representation, which can be filtered by
components of the calculated system.
Hydration and response of an experimental Sandwich shaft-sealing system at the Mont Terri rock laboratory
Authors: Hinze Matthias , Wieczorek Klaus , Emmerich Katja , Hesser Jürgen , Furche Markus , Shao Hua , Jaeggi David , Schefer Senecio , Nagel Thomas , Mayor Juan Carlos , Norris Simon , Chang-Seok Kim , Schädle Philipp , García-Siñeriz José Luis , Schuhmann Rainer , Königer Franz , Glaubach Uwe , Rölke Christopher , Diedel Ralf 
Published: September 2023

Abstract. A necessary and important component for the closure of deep geological repositories (accessed by a shaft) is a shaft-sealing system that limits the fluid inflow from the adjacent rock to the repository in the early post-closure phase and delays the release of possibly contaminated fluids from the repository at a later stage. The Sandwich system developed at Karlsruhe Institute of Technology (Schuhmann et al., 2009) is a multicomponent barrier that can contribute to this sealing function and is considered as part of the German shaft-sealing concept (Kudla and Herold, 2021). Its functionality has been assessed in a large-scale in situ test (the SW-A experiment) carried out at the Mont Terri rock laboratory (MTRL) in cooperation with international partners as part of the Sandwich-HP project since July 2019. The in situ test was planned as part of an international pre-project (Emmerich et al., 2019) and is
accompanied by a laboratory- and semi-technical-scale test program as well as by model simulations. The setup of the SW-A experiment comprises two shafts of 1.18 m diameter
and 10–12.6 m depth in the Sandy Facies of the Opalinus Clay at MTRL. Each shaft contains a Sandwich seal as well as a hydration system in order to realize fluid inflow from the bottom (Fig. 1a). The implemented Sandwich system is characterized by an alternating arrangement of four low-permeability sealing segments (DS) made of bentonite and five equipotential segments (ES) made of fine-grained quartz sand with higher hydraulic conductivity. Fluid entering an ES is supposed to be evenly distributed over the cross section and, thus, the interface of the adjacent DS, leading to a homogeneous hydration and swelling of the DS. Water bypassing a DS and high hydraulic loads can be absorbed and distributed by the next ES. In the experiment, the sealing systems and the surrounding rock are intensely monitored (e.g., geophysics, water content, relative humidity and temperature, pore pressure, stress, and displacement) in order to investigate the saturation process and assess the interaction of the sealing system and the host rock. Hydration of the system in Shaft 1 started in May 2021, and the monitoring system showed a relatively fast saturation of the lowermost ES and DS and a water bypass in August 2021 (Fig. 1b); this was accompanied by slower saturation of the upper ES and DS, swelling of the DS and a pore pressure increase in the surrounding rock. Hydration of Shaft 2 started in May 2023. Data and experience obtained to date will be presented.
Demonstrating the possibility of safe operation in the first phase of the site selection procedure in Germany
Authors: Werres Michael , Fahrendorf Frederik , Lohser Thomas , Rühaak Wolfram 
Published: September 2023

Abstract. The Federal Company for radioactive waste disposal (BGE) is responsible for
the search for a site with the best possible safety for the disposal of
high-level radioactive waste in Germany. The site selection procedure is
regulated in a law that was adopted by the German Federal Parliament
(Repository Site Selection Act – StandAG, 2017, last updated 2020
(StandAG)) and aims to be a participatory, transparent, learning, and
self-questioning process based on scientific expertise. The first step of
the first phase of the site selection procedure was completed in September
2020 and resulted in the identification of sub-areas that give reason for
expecting favourable geological conditions for the long-term storage of nuclear
waste in the sub-surface. These sub-areas cover approximately 54 % of
Germany and are located in three different host rocks: rock salt–halite,
claystone, and crystalline rock. The challenge for the next step is to find
suitable siting regions within the previously determined sub-areas that are
then considered further in the next phase of the site selection procedure
(Hoyer et al., 2021). The preliminary representative safety analyses in Phase I, Step 2 of the site
selection procedure require according to Section 7 (6) No. 4 EndlSiUntV that
“the basic possibility of safe operation shall be demonstrated, but a
complete operational safety analysis does not need to be performed”. The
method is described in BGE (2022a, b) and can be summarized as
follows. The demonstration of the basic possibility of safe operation is carried out
within the framework of the representative safety analyses for the
individual aspects of operational safety in different degrees of detail. The
non-radiological aspects of operational safety, which are, for example,
derived from occupational health and safety, mining law and fire protection,
a site-independent consideration of the regulatory basis and the derivation
of corresponding actions, are considered requirements for and are taken
into account by the preliminary repository design according to Sect. 6 (4)
EndlSiUntV. To demonstrate the basic possibility of safe operation for the operational
safety aspects “radiation protection” and “release of radioactive
substances” in the investigation areas to be considered, a general
catalogue is compiled that summarizes possible events and actions to fulfill
the requirements for operational safety. This general catalogue is independent
of location and coverage of all host rocks and repository concepts. From this general catalogue, possible specific events are identified for each
individual investigation area, and the necessary actions are derived. In
addition to the demonstration of the basic possibility of safe operation,
the robustness of operational safety within the investigation area is
evaluated in a second step.
Panel: safeguarding nuclear waste management
Authors: Niemeyer Irmgard 
Published: September 2023

Abstract. When the world's first encapsulation plant and geological repository (EPGR)
for spent nuclear fuel disposal will start operations in Finland in a few
years, this will also be the first facility of this kind for which
international safeguard measures (e.g. Niemeyer et al., 2021) will be implemented. This two-part panel
takes this as an opportunity to focus on the approaches, concepts, methods
and technologies for safeguarding nuclear waste management. The first part discusses the current state and challenges in safeguarding
spent fuel storage facilities, encapsulation plants and geological
repositories and elaborates on the recent progress of safeguard developments
and implementation, as well as existing gaps. Panellists will address the
following questions. (i) Which safeguards approaches are currently developed for or implemented at spent fuel storage facilities, encapsulation plants and geological repositories? (ii) How do we make best use of safeguards concepts, such as safety–security–safeguards (3S) and safeguards by design (SBD), in nuclear waste management? (iii) Lastly, what are the most important research and development (R&amp;D) activities regarding safeguards methods and technologies in nuclear waste management (related to the technical readiness levels (TRL) 4–8)? The second part then looks at future challenges of safeguarding nuclear
waste management in the medium and long term and develops some priorities in order to meet these challenges, based on the following questions. (i) Which challenges are on the horizon regarding safeguards implementation at spent fuel storage facilities, encapsulation plants and geological repositories in
the medium and long term? (ii) What are medium- and long-term challenges of
safeguards implementation from the operator's point of view? (iii) What are the most promising methods and technologies for safeguarding nuclear waste management in the medium- and long-term future (related to the technical readiness levels (TRL) 1–4)? Both parts will include panellists from safeguards inspectorates, national safeguards authorities, the nuclear industry and research entities. The panel will be held with the Final Disposal Working Group of the
European Safeguards Research and Development Association (ESARDA)
(https://esarda.jrc.ec.europa.eu/working-groups/final-disposal-fd_en, last access: 24 August 2023).
Economics of new nuclear power plants – assessment of investments into Generation III, small modular reactors and non-light-water reactors
Authors: Böse Fanny , von Hirschhausen Christian 
Published: September 2023

Abstract. Given the need to combat climate change, as recently stressed again within the IPCC (2023) report, and the recent energy price increases for electricity and natural gas through the war in Ukraine (ECB, 2022), investments into new nuclear power plants are a considered option for future energy systems in some countries. In this paper, we discuss economic aspects of such investments, differentiating between three different types of reactor technology, as described in the following:
i. At present, the only viable option for an investment would be “Generation III” reactors, i.e., light-water reactors with high capacities (in the range of or above 1000 MW). The most recent projects of that type have been very expensive, though, and there is a controversy about whether future ones will become competitive (Wealer et al., 2021; Duan et al., 2022). Economic questions relate to economies of scale and the differences in costs between western reactors (USA, Europe) and those in Russia and China.ii. In some countries, the development of and subsequent investments in light-water reactors of small power rating (<300 MW) are pursued (e.g., in the US, Canada and the UK). These are sometimes called “small modular reactors” in the recent literature (Chu, 2010; IAEA, 2022). These concepts are surrounded by high uncertainty, and the paper proposes a methodology for economic analysis, based on previous literature (Rothwell, 2016; Roulstone et al., 2020; Boarin et al., 2021).iii. A third option for newly built reactors is represented by non-light-water reactors, amongst which the classical sodium-cooled fast neutron reactor (“fast breeder”) is the most advanced type as well as high-temperature reactors and molten-salt reactors. With the establishment of the GenIV International Forum in 2001, 14 member states, including the USA, China, Russia, the EURATOM states, and the United Kingdom, have joined forces with the shared objective of further developing non-light-water reactor concepts. The paper provides a methodology to assess the competitiveness of fast reactors and extends it to other non-light-water reactors.
The paper concludes with an assessment of the economics of new nuclear power plants going forward. Particular consideration is given to the aspects of
decommissioning from the very outset, i.e., the planning of the new reactor. In
that context, the paper will address the interdependencies between technology choices and storage issues, for example volume composition.
Technological readiness of alternative reactor concepts
Authors: Englert Matthias , Pistner Christoph 
Published: September 2023

Abstract. Some alternative reactor concepts are frequently discussed in the literature as relevant for the disposal of high-level radioactive waste. We present results on the technological readiness of and research and development on those reactor concepts from a project commissioned by the Federal Office for the Safety of Nuclear Waste Management on novel reactors (Pistner et al., 2023). The focus is on 7 technology lines and 10 specific reactor concepts within those lines. These are sodium-cooled fast reactors (SFRs), lead-cooled fast reactors (LFRs), gas-cooled fast reactors (GFRs), very high-temperature reactors (VHTRs), super-critical water-cooled reactors (SCWRs), molten-salt reactors (MSRs) and accelerator-driven systems (ADSs). For all technology lines considered, extensive research and development work has been taking place for several decades and in some cases since the middle of the last century. Depending on the technology line, technical test stands for individual phenomena have been built and operated and so have smaller experimental reactors and larger demonstration reactors. Nevertheless, until today no commercially competitive reactor concept exists in the field of alternative reactor concepts. The most extensive technical experience is available for the SFR and VHTR technology lines. However, proof of reliable operation under economic boundary conditions is still required for SFRs and VHTRs. For other technology lines, neither has technical feasibility in the form of a demonstration reactor been demonstrated so far (LFR, MSR) nor are more extensive findings from smaller experimental reactors available (GFR, SCWR, ADS). To plan, license, construct and operate such experimental and demonstration reactors, a period of at least 1 to 2 decades must be assumed for each reactor project and probably substantially more based on historical experience. It has been shown that developers' schedules are often characterized by overly optimistic assumptions, that developments are delayed by years or even decades, and that in many cases specific approaches are discontinued completely because the underlying technological difficulties could not be overcome. Thus, the time still required for the development of alternative reactor concepts is probably in the range of several decades. Against this background, it cannot be assumed that such reactor concepts will be used on a relevant scale by the middle of this century. Additionally we will present general results of this study regarding criteria such as safety, fuel supply and waste disposal, proliferation, and
costs and point out advantages and disadvantages of those systems over light-water reactors.
How to transfer knowledge to Generation Z
Authors: Wiesel Hendrik 
Published: September 2023

Abstract. With this paper, we aim to raise awareness of the challenges of generational transition in the German nuclear industry. We
present potential solutions for transferring and preserving knowledge in the future. For approximately 60 years, Germany has operated nuclear facilities
successfully and safely. Germany phased out the peaceful use of nuclear
energy in 2023 by shutting down the last three nuclear power plants. At the
same time, a generational shift is imminent within the next 5–10 years, as a significant number of knowledgeable experts will be retiring.
Simultaneously, the first “fully digitalized” Generation Z, whose learning methods and preferences differ significantly from the previous generation (see Fig. 1), will enter the job market (McKinsey &amp; Company et al., 2018). This requires the development and establishment of new methods and didactics (Chillakuri, 2020). Furthermore, educational institutions in Germany are reducing their curriculum offerings in the field of nuclear technology. This necessarily leads to the challenge of introducing and training a growing number of
newcomers with limited prior knowledge in the complex field of nuclear
technology. In our investigation, we focused on the development of new
learning concepts. Various research approaches, studies, and internal
evaluations were considered that addressed the learning preferences and
styles of Generation Z (McKinsey &amp; Company et al., 2018; Chillakuri, 2020; Cilliers, 2017). Generation Z is characterized by a strong commitment to digital
technologies, a high affinity for collaboration, and a preference for
interactive and visual learning methods. Unlike previous generations,
Generation Z increasingly favours informal, flexible, and context-based
learning (Cilliers, 2017). To address these attributes, a multilevel learning concept was developed. The concept includes various digital and asynchronous (on-demand) formats
that facilitate an attractive and flexible learning environment. A variety
of media types, such as e-learning videos, podcasts, animated films, and
virtual realities, were well-received by the participants. Attention span,
which has changed compared to previous generations, was taken into account.
To maintain attention, playful elements (gamification) were inserted into
the format. Additionally, online expert discussions were established, as
personal exchanges convey experiences and emotions, leading to a higher
level of memorability. The future of nuclear safety and competence in Germany depends on a
successful transfer of knowledge in the coming years. A lack of adaptation
of learning methods and didactics to the needs of current and future
generations risks the loss of a significant portion of accumulated
expertise. This loss poses a risk to nuclear safety, can drive up costs, and can lead to project delays of several years.
Geodata for the public – best practice examples from GIS and web applications
Authors: Maurer-Rurack Ute , Schilling Maik 
Published: September 2023

Abstract. Public participation is one of the requirements for the search for a final
repository to succeed. This is because the site selection will only be
accepted if the procedure is transparent and the decision for a safe
location is comprehensible. Geo- and socioscientific information
plays an important role in the site selection process (StandAV) in Germany and
must therefore be prepared in a way that is understandable to the public.
Geographic information systems (GISs) and web applications are essential
tools here for making complex geoscientific and socioscientific information
available to the public in a comprehensive, appealing and transparent way. This workshop is intended to provide an opportunity to present, share and learn
from each other by selected GIS and web applications related to symposium's
topic: resilient safety. The safeND symposium is an opportunity to present
applications to a broader audience and to discuss opportunities and
challenges of GIS and web applications bringing general and scientific
information closer to the public. Who can be reached, who will not be
reached? And why? The agenda is as follows (workshop duration: 120 min):
I. introduction (5 min)II. presentations (each 15+10 min, 25 min total):
1. Marian Graumann, SKD (Satellite-based Crisis and Situation Service): Web presentation of a worldwide overview of nuclear power plants (NPPs) and focus on the actual available data to the public in Germany2. Christoph Strobl, BfS (Federal Office for Radiation Protection): Remapping of the Chernobyl Exclusion Zone: georeferenced comparison of the spatial distribution of 137Cs with previous measurements3. Andreas von der Dunk, NAGRA (National Cooperative for the Disposal of Radioactive Waste, Switzerland): Lessons learned from using GIS-based web applications to promote stakeholder participation during the site selection process for a deep geological repositoryIII. wrap-up (10 min)IV. demonstration in detail of the GIS and web-applications (30 min).