bluuebunny/crossref_metadata_2025 huggingface dataset:
UNLOCKING THE POTENTIAL OF E-COMMERCE IN RURAL MADHYA PRADESH: CHALLENGES AND OPPORTUNITIES FOR FMCG COMPANIES IN 2023
Authors:   Department of Commerce Vikram university, Ujjain Madhya Pradesh, Kothari Neha , Pathak Abhay ,   Swami Vivekanand Government commerce College, Ratlam, Madhya Pradesh
Published: September 2023

With the rapid advancement of technology and the increasing penetration of the internet, ecommerce has emerged as a transformative force in the global business landscape. While its impact is evident in urban areas, the potential of e-commerce in rural regions remains largely untapped. This abstract focuses on exploring the challenges and opportunities faced by fastmoving consumer goods (FMCG) companies in leveraging e-commerce to unlock the potential of rural Madhya Pradesh, India's central state, in 2023.Rural Madhya Pradesh presents a unique set of challenges for FMCG companies aiming to tap into the e-commerce market. These challenges include limited internet connectivity, low digital literacy rates, inadequate transportation infrastructure, and fragmented supply chains. Additionally, rural consumers often exhibit different purchasing behaviours and preferences compared to their urban counterparts, necessitating tailored marketing strategies and product offerings. Furthermore, understanding the unique needs and aspirations of rural consumers is crucial for FMCG companies to succeed in this market. Tailoring product offerings to cater to local preferences, affordability, and value for money can enhance customer engagement and brand loyalty. Moreover, implementing localized marketing strategies, including vernacular language support and targeted advertising campaigns, can effectively communicate the value proposition of e-commerce to rural consumers. In conclusion, unlocking the potential of ecommerce in rural Madhya Pradesh requires FMCG companies to navigate a range of challenges while capitalizing on emerging opportunities. By addressing the barriers related to infrastructure, connectivity, and consumer behaviour, and by adopting localized strategies, FMCG companies can establish a strong foothold in this untapped market, driving economic growth and transforming the rural retail landscape in 2023
DESCRIPTIVE ANALYSIS OF CYBER SWACHHTA KENDRA - AN INITIATIVE BY GOVERNMENT OF INDIA.
Authors:   Department of Economics Vivekanand Education Society's College of Arts, Science and Commerce (Autonomous) Chembur, Jayesh Ganatra Heena
Published: September 2023

Cyber Swachhta, is a very important initiative taken by the government of India after launching the digital India where the government has found various challenges related to cyber security, cleaning, and malware analysis. "Cyber Swachhta Kendra" (Center for Botnet Cleanup and Malware Analysis) is part of the Government of India's Digital India initiative under the Ministry of Electronics and Technology Information, which aims to create security by tracking and tracing botnet infections. Malware is a malicious software basically computer programs that are designed to damage the computer without the user's continent and control by cyber criminals. CERT-In (CSK) celebrating "Cyber Swachhta Pakhwada" during 01-15 February 2023. As a people of India, people should follow the guidelines related to Cyber Swachhta
MEASURING THE FINANCIAL PERFORMANCE OF BHARAT SANCHAR NIGAM LTD. IN BHOPAL USING RATIO ANALYSIS
Authors:   Research Scholar Department of commerce Barkatullah University, Bhopal (M.P), Masih Stella
Published: September 2023

This study use ratio analysis to evaluate Bharat Sanchar Nigam Ltd.'s (BSNL) financial standing in Bhopal. Financial health was assessed by looking at liquidity, profitability, and solvency measures for 2018, 2019, and 2020. The ratio research showed that BSNL has serious money problems since the company's liquidity, profitability, and solvency ratios are all poor. A fall in the company's current ratio and quick ratio over time indicates that meeting short-term commitments may be difficult for BSNL. The company has been losing money and failing to generate positive returns for its investors since its net profit margin ratio, return on assets ratio, and return on equity ratio are all below zero. The increasing debt-to-equity ratio, debt-to-total-assets ratio, and interest coverage ratio all indicate that the company is more dependent on debt financing rather than equity funding. This indicates that the corporation may have trouble generating enough revenue to meet its interest expenditures. Based on the results of this study, BSNL should make certain strategic adjustments to boost its bottom line. The recommended measures, such as better working capital management, debt reduction, revenue growth, and customer service improvement, may aid the firm in overcoming its financial difficulties. BSNL's overall financial health is in a vulnerable state, and the corporation has to take immediate measures to strengthen its bottom line.
The effect of propolis addition to the laying-hen diet on performance, serum lipid profile and liver fat rate
Authors: Bölükbaşı Şaziye Canan , Ürüşan Hilal , Apaydın Yıldırım Betül
Published: September 2023

Abstract. The aim of this study was to evaluate the effect of propolis (P) on
performance, egg quality parameters, serum lipid profile, some liver enzymes
and liver fat ratio. One-hundred-and-twenty Lohmann (LSL) laying hens were divided into five
groups, and each group consisted of six subgroups. The control group was fed
basal diet. The other groups were fed high-energy (HE) diets to induce fatty
liver syndrome, and 0, 100, 200 and 300 mg kg−1 of propolis were supplemented with
high-energy feeds. During the 8-week trial, feed and water
were given ad libitum. It was determined that egg production and feed conversion ratio were
decreased in the high-energy feed group without the addition of propolis.
The highest egg production was found in HE + 100 and HE + 200 mg kg−1 of P groups. It was found that liver fat ratios were higher in the group
fed with HE + 0 mg kg−1 of P feed (P<0.01) than other groups. But the
addition of P decreased the liver fat rate significantly. The highest very
low density lipoprotein (VLDL), triglyceride (TG) and low-density
lipoprotein (LDL) values were found for the HE + 0 mg kg−1 of P group. The
addition of 200 mg kg−1 of P to high-energy feed increased glutathione
(GSH), superoxide dismutase (SOD), catalase (CAT) and glutathione peroxidase
(GPx) values. In conclusion, high-energy feed adversely affected egg production and liver
fat ratio, but the addition of 100 or 200 mg kg−1 of propolis improved egg
production and decreased liver fat ratio.
Measurement report: Influence of long-range transported dust on cirrus cloud formation over remote ocean: Case studies near Midway Island, Pacific
Authors: Shen Huijia , Yin Zhenping , He Yun , Wang Longlong , Zhan Yifan , Jing Dongzhe
Published: September 2023

Abstract. Cirrus clouds play an essential role in regulating the global radiative balance and climate by both reflecting the incoming shortwave solar radiation and reserving the outgoing longwave radiation in the atmosphere. The cirrus-induced net radiative forcing is mainly determined by their microphysical properties, which are strongly associated with the competition between two ice-nucleating mechanisms, i.e., heterogeneous and homogeneous nucleation. However, it is still not well understood whether the long-range transoceanic dust can potentially urge heterogeneous nucleation to the initial ice formation in cirrus clouds even farther over vast remote ocean regions and the response of dominant ice-nucleating mechanism to the concentrations of available ice nucleating particles (INPs). Here we report on the influence of transpacific dust plumes on the ice formation in cirrus clouds via heterogeneous nucleation based on the combined observations of space-borne instruments, i.e., the Cloud-Aerosol Lidar with Orthogonal Polarization (CALIOP) and Cloud Profiling Radar (CPR). Two cases near Midway Island (28.21° N, 177.38° W), located in the central Pacific, are studied, in which the long-range transported dust plumes originate from intense Asian dust events. For both cases, partial cloud parcels show the typical in-cloud ice crystal number concentrations (ICNC) of <100 L-1 for heterogeneous nucleation with a good agreement (within an order of magnitude) of in-cloud ICNC and nearby dust-related INP concentration (INPC) values, indicating that dust-related heterogeneous nucleation is dominated in ice formation. In addition, for the other parts of clouds without sufficient INP supply, homogeneous nucleation can still be dominated with ICNC values exceeding 300 L-1. Therefore, dust events with sufficient intensity are capable of conducting long-range transport and influencing cirrus formation over remote ocean regions. This study shows that the natural supply of effective INPs to the upper troposphere, such as long-range transported dust aerosols can increase the cloud cover to reflect more solar radiation over oceanic regions and modulate the microphysical properties of cirrus clouds through different ice-nucleating regimes, both of which may further result in a cooling effect on global climate and should be well considered in climate evaluation.
Assessing the impact of climate change on high return levels of peak flows in Bavaria applying the CRCM5 Large Ensemble
Authors: Willkofer Florian , Wood Raul Roger , Ludwig Ralf
Published: September 2023

Abstract. Severe floods with extreme return periods of 100 years and beyond have been observed in several large rivers in Bavaria in the last three decades. Flood protection structures are typically designed based on a 100-year event, relying on statistical extrapolations of relatively short observation time series while ignoring potential temporal non-stationarity. However, future precipitation projections indicate an increase in the frequency and intensity of extreme rainfall events, as well as a shift in seasonality. This study aims to examine the impact of climate change on the 100-year flood (HF100) events on 98 hydrometric gauges within the Hydrological Bavaria. A hydrological climate change impact (CCI) modelling chain consisting of a regional single model initial condition large ensemble (SMILE) and a single hydrological model was created. The 50 equally probable members of the CRCM5-LE were used to drive the hydrological model WaSiM to create a hydro-SMILE. As a result, a database of 1,500 model years (50 members x 30 years) per investigated time period was established for extreme value analysis (EVA) to illustrate the benefit of the hydro-SMILE approach for a robust estimation of the HF100 based on annual maxima (AM), and to examine the CCI on the frequency and intensity of HF100 in different discharge regimes under a strong emission scenario (RCP8.5). The results demonstrate that the hydro-SMILE approach provides a clear advantage for a robust estimation of the HF100 using empirical probability on 1,500 AM compared to its estimation using the generalized extreme value (GEV) distribution on 1,000 samples of typically available time series size of 30, 100, and 200 years. Thereby, by applying the hydro-SMILE framework the uncertainty from statistical estimation can be reduced. The CCI on the HF100 varies for different flow regimes, with snowmelt-driven catchments experiencing severe increases in frequency and intensity, leading to unseen extremes that impact the distribution. Pluvial regimes show a lower intensification or even decline. The study highlights the added value of using hydrological SMILEs to project future flood return levels.
FESOM2.1-REcoM3-MEDUSA2: an ocean-sea ice-biogeochemistry model coupled to a sediment model
Authors: Ye Ying , Munhoven Guy , Köhler Peter , Butzin Martin , Hauck Judith , Gürses Özgür , Völker Christoph
Published: September 2023

Abstract. This study describes the coupling of the process-based Model of Early Diagenesis in the Upper Sediment (MEDUSA version 2) to an existing ocean biogeochemistry model consisting of the Finite-volumE Sea ice-Ocean Model (FESOM version 2.1) and the Regulated Ecosystem Model (REcoM version 3). Atmospheric CO2 in the model is a prognostic variable which is determined by the carbonate chemistry in the surface ocean. The model setup and its application to a pre-industrial control climate state is described in detail. In the coupled model 400 PgC are stored in equilibrium in the top 10 cm of the bioturbated sediment, mainly as calcite, but also to 5 % as organic matter. Simulated atmospheric CO2 is in equilibrium at 286 ppm in the coupled simulation, which is close to the initially assumed value of the pre-industrial CO2 level. Sediment burial of carbon, alkalinity and nutrients in the coupled simulation is set to be partly compensated by riverine input. The spatial distribution of biological production is altered depending on the location of riverine input and the strength of local nutrient limitation, while the global productivity is not affected substantially.
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.
Identifying safety-relevant knowledge gaps concerning radionuclide mobility – bringing together fundamental research and application in repository safety analysis
Authors: Philipp Thimo , Pekala Marek
Published: September 2023

Abstract. The mobility of radionuclides in a nuclear waste repository is strongly influenced by their chemical form (e.g. oxidation state and speciation), which determines their solubility and chemical interactions with mineral
surfaces. To date, significant efforts have been made to investigate
the mechanisms (e.g. sorption and diffusion) underlying radionuclide retention.
However, knowledge gaps persist, especially under complex environmental
conditions, as may be expected in a deep geological repository (e.g.
the complexation of radionuclides with organic compounds, the influence of elevated
temperature and the effects of high ionic strength). In order to make
reliable predictions about radionuclide mobility and, consequently, about
post-closure repository safety, it is necessary to identify, evaluate and,
where necessary, close these knowledge gaps. This workshop aims to bring together experts in both fundamental research
and its applications to repository safety. It intends to facilitate
knowledge exchange between the two fields, promoting more coordinated and
goal-oriented safety research. Participants are invited to share their
knowledge about the need for further experimental and computational
investigations as well as their insight into the data requirements for reliable transport
models and implications for safety assessment.
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&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.
Investigations of aged metal seals for transport package safety assessment
Authors: Rolle Annette , Neumeyer Tino , Ballheimer Viktor , Wille Frank
Published: September 2023

Abstract. Acceptable limits for activity release from transport casks for high-level
radioactive material specified in the IAEA regulations must be kept by the
integrity of cask body and the cask sealing system. BAM – the German
competent authority for mechanical, thermal and containment assessment of
packages liable for approval – verifies the activity release compliance with
the regulatory limits. One of the fundamental aspects in assessment is the
specification of conservative package design leakage rates. To ensure the required package tightness for both storage and transport of
the cask before and after storage, usually metal seals of the
HELICOFLEX® type are used. Due to long-term use, the seal behaviour is influenced by temperature and time. The mechanical and thermal loadings associated with the routine, normal and accident conditions of transport specified in the regulations can have a significant effect on the leak tightness of the sealing system. Whereas the safety for application of new, non-aged HELICOFLEX® seals is verified sufficiently, there are still technical data gaps concerning the efficiency of aged HELICOFLEX® seals. BAM performed experiments to learn more about the sealing efficiency of aged
HELICOFLEX® seals with aluminium and silver outer jackets. The seals were compressed in test flanges, and for artificial ageing the complete flange systems were stored in an oven for several months at a high temperature. During the compression and decompression tests after the ageing, load-deformation characteristics of the seals and leakage rates were measured. With these tests a load situation was simulated, which can occur in the regulatory drop test of the cask: under high-impact loads the bolted lid can lift a little for a short moment, allowing a little movement of the seal so that the contact area can change before compressing again. The poster presentation will show details about test conditions and first
results.
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 & 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 & 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).
Improvement by public participation? The case of the German calculation basis for the dose assessment for final disposal of high-level waste (HLW)
Authors: Hormann Volker , Kogiomtzidis Anna , Walther Clemens
Published: September 2023

Abstract. In April 2022, the Federal Office for the Safety of Nuclear Waste Management (BASE) invited the public to comment on the previously issued draft of the “Berechnungsgrundlage für die Dosisabschätzung bei der Endlagerung von hochradioaktiven Abfällen” (Calculation basis for dose assessment of the final disposal of high-level radioactive waste); 360 comments and suggestions were submitted, especially concerning radioecological modelling. In a table that was made publicly available, many of the issues raised were commented on, but not all of them. At the end of June 2022, an expert
workshop was held at BASE, where a subset of the comments was also
discussed. In December 2022, BASE issued the final version of the
“Berechnungsgrundlage”, unfortunately without any further feedback on why
changes were made or not. In the present contribution we will analyse this
participation process, taking into account both the aspect of implementation and the radioecological models used. Only a rather limited number of suggestions have been considered. To name a
few, there has been no revision of the radioecological parameters that are
being used in German administrative regulations and that have scarcely been
updated within the past 40 years. Also, a proposed method for better
estimating the retention times of radionuclides in soils with the help of
distribution coefficients that have been tabulated by the IAEA but that can also be measured or calculated for special soils with the help of geochemical models was ignored. Still, the final version of the
“Berechnungsgrundlage” assumes only three classes of retention times
(10–8, 10–9, and 10–10 s) that do not appropriately reflect the behaviour of the individual radionuclides. On the other hand, the proposal to consider an additional contamination
path, namely the capillary transport of radionuclides from groundwater into
the root zone, has been included. In the workshop we would like to raise the question of whether and how this kind of process might be improved. Specifically, in view of the delay in site selection, the haste with which the project was completed should be
discussed.
Last century's German citizens' dialogue on nuclear energy revisited: new lessons learnt?
Authors: Meyer Jan-Henrik , Oertel Britta
Published: September 2023

Abstract. The German Site Selection Act for a Nuclear Repository of 2017 aims, among
other objectives, to find a solution that is supported by a broad social
consensus and can thus also be tolerated by those affected. Public
participation is considered indispensable when planning and building a
nuclear waste repository today. However, what is now even laid down by law
has taken some time to emerge. The roots of today's guiding principles on
public involvement lie first of all in the nuclear energy controversy of the
1970s and 1980s, which marked the first major societal conflict about
technology in (West) Germany and, in terms of its consequences, has shaped
the course of events up to the present day. Much of the experience with
public engagement, its pitfalls and chances, has been largely forgotten. This paper seeks to address the present lack of knowledge about past
government-funded public engagement on nuclear energy. It presents, for the
first time, key findings from a 3-year interdisciplinary collaborative
research project, funded by the Federal Office for the Safety of Nuclear
Waste Management (BASE), on Germany's first information and dialogue
campaign on this topic, the “Citizens' Dialogue on Nuclear Energy”
(“Bürgerdialog Kernenergie”), which ran from the mid-1970s until the early 1980s. This research is based on comprehensive archival work in numerous state and non-state archives across Germany, a vast array of published materials, and oral history interviews. The paper will discuss why the campaign was started, which (international) models it drew on, which instruments it relied on, and which obstacles and dilemmas it faced. It will present where and to what extent the campaign was able to achieve its goals and where – and why – it failed. The “Citizens' Dialogue” was initially nationwide in scope. From 1977 onwards, activities primarily focussed on the region around Gorleben, where West Germany's nuclear waste repository was initially planned to be located (this decision being finally revoked in 2020). The paper argues that the government-funded campaign was based on two assumptions, which shaped its structure. First, relying on the then conventional knowledge deficit model, governments and experts assumed that citizens needed to be better informed to accept the need for nuclear expansion and lose their supposedly irrational fears regarding nuclear safety. Second, social democratic governments in Europe viewed the involvement of citizens in debates about technology, quality of life and planning for the future as new democratic territory. Juxtaposing past and present experiences with government-funded public engagement, the paper seeks to extract and discuss lessons that may be drawn from the history of past public engagement for the search for a new repository site – in Germany and elsewhere.
Let's do science communication
Authors: Kähler Esther , Wagenknecht Katherin , Weißpflug Maike , Hellebrandt Stefan
Published: September 2023

Abstract. Germany is looking for a final repository for highly radioactive waste. This is a task for society as a whole, requiring a broad participation process and, above all, a scientific basis. The process is still in its early stages, but as the possible siting regions are narrowed down, public
attention will increase significantly in the coming years. This workshop
explores the role of science communication within the search process. Above all, the complex and scientific process must be transparent,
comprehensible and understandable: science communication is a key success
factor in communicating scientific subject matter. The search for a
repository involves questions of geology as well as questions of scientific
planning criteria and the legal basis for participation. Also relevant are
questions of ecological, economic and social regional development at the
potential site. For the support and participation in this interdisciplinary and
transdisciplinary process, it is indispensable to formulate the contents and
positions in a generally understandable way. In this workshop we will discuss the complex role of science communication
in the repository search process. How can scientific content from different
disciplines be communicated? Which formats are suitable for communicating
technical content in transdisciplinary discourses? What needs to be
communicated in the context of the search for a final repository? What
content is essential for understanding the process? The workshop addresses
the participants as communicating scientists with practical experience or
specific questions and invites the participants to deal with these questions in a playful way: the basis for the workshop is a game plan that depicts and explains the phases and the course of the process and presents the most important information of the scientific process. In the format of a world café, the participants will experience to which extent science communication plays a role as an essential factor in the procedure. There will be two scenarios to play: on the one hand, the
participants will be asked to deal with the question of which forms and
contents are required for the procedure to be conducted successfully. On the other hand, it is about dealing with the risks and challenges of misguided science communication. For both scenarios, the task is to identify essential formats and content as well as points in time. The participants will be asked to formulate concrete examples. The player will go through each step in the search for a repository and
discuss their influence as the communicating scientist on the success of the search. How can people be influenced by communication of risk topics, and
therefore how can this influence people's attitude towards the process? In addition to personal experience, scientific questions regarding
necessary information during the phases of the search will be generated in that format. How can science or science communication support the different steps of the search?