Waste Inventory Research Articles

Identification and Quantification of Multiphase U(VI) Speciation on Gibbsite with pH Using TRLFS and PARAFAC of Excitation Emission Matrices.

The significant abundance of uranium in radioactive waste inventories worldwide necessitates a thorough understanding of its behavior. In this work, the speciation of uranyl(VI), (UO22+) in a gibbsite system under ambient conditions has been determined as a function of pH by deconvolution and analysis of luminescence spectroscopic data. Uniquely, a combined experimental and statistical approach utilizing time-resolved luminescence spectroscopy and parallel factor analysis (PARAFAC) of excitation emission matrices has been successfully utilized to identify four separate luminescent U(VI) species in the uranyl-gibbsite system for the first time. The speciation of all luminescent U(VI) species in an environmentally relevant system over a pH range of 6-11 is discerned through the analysis of emission fingerprints at low temperature (20 K). Comparison of the deconvoluted luminescence spectra with mineral standards and geochemical models of the system allows the assignment of the luminescent chemical species as metaschoepite, Na-compreignacite, surface adsorbed ≡AlO2-UO2(OH) and ≡AlO2-UO2(CO3)24- complexes, with assignments supported by fitting of extended X-ray absorption fine structure data. The combined spectroscopic techniques in this study show that assignment and quantification of uranyl(VI) species in a sorption system over a large pH range can be accurately achieved using PARAFAC to deconvolute a three way emission spectroscopic data set.

Determination of the type of radioactive nuclei and gamma spectrometry analysis for radioactive sources

Determining the type of radioactive nuclei is the second activity after the inventory of radioactive waste in Kosovo, their location and the number of radioactive sources. Before starting any type of radioactive waste action, it is necessary to determine the content of their activity, the type of radioisotope, physical and chemical form and the risks associated with their management. The realization of this is achieved as a combination of quality assurance processes, the inventory of the radioisotope and its activity that is present in the waste, the composition of the waste material and direct measurements. This serious activity was carried out entirely in the field and was undertaken due to the lack of source certification or any other indication of their classification and activity. The process of determining the type of radioactive nuclei helps to realize a more effective characterization of them as well as to determine the path of waste management. The probability that a gamma radiation detector interacts with it to produce a pulse represents the effectiveness of the detector.

Analisis Pengurangan Waste Proses Produksi Pada PT SP Manufacturing

PT SP Manufacturing is a manufacturing company that operates in the field of wire harness production. When making wire harnesses at PT SP Manufacturing, waste still occurs. Waste in the production process is one of the biggest problems this company wants to solve. A defective product is a product that does not meet wire harness production standards so it cannot meet customer demand, and requires more space before rework is carried out, which causes inventory waste (Unnecessary Inventory). Reduced productivity and higher production costs are the result of this waste. The aim of this research is to use value stream mapping to identify waste in the production process and apply lean manufacturing techniques to reduce it. The results obtained are based on identification and analysis of existing problems as well as alternatives and improvements based on the formulation and objectives in the research. The largest waste in the wire harness production process of PT.SP Manufacturing is waste with a weight score of 60.89%, unknown inventory waste with a weight score of 39, 12%. The causal factors are workers who lack concentration, apply excess solder paste to the wire terminals, workers who pursue targets without paying attention to quality, resulting in defective products that require rework. The recommendations given to the company according to the fishbone diagram are proposed improvements to the wire harness production process to reduce defects and unnecessary inventory which refers to people, machines, methods and materials.

Waste Assessment of 1.275 MWP PV Plant: Case of Northern Cyprus

PV technologies gained significant importance during the last 2 decades by providing clean and renewable electricity. However, PV panels complete their operational life in 25-30 years and transform into hazardous waste for both human health and environment. Management of PV Waste is an important environmental issue which requires a detailed inventory of the PV Waste. In this study, the PV Waste inventory of 1.275 MWP PV Plant installed in Serhatköy Region of Northern Cyprus, on May 2011, is investigated. Results showed that, this plant will complete its operational lifetime in 13-18 years and generate the first bulk PV Waste in Northern Cyprus. Inventory analysis of the Serhatköy PV Plant revealed that 63476 kg of glass,16807 kg of aluminum, 9230 kg of steel, 6640 kg of EVA, 807 kg of silicon, and 746 kg of copper can be recycled and recovered. Also, this study revealed that Northern Cyprus can catch the PV Waste Management targets of the European Union with a down-cycling PV Waste Strategy.

Radioactive Waste Management Challenges: Nigerian Case Study

Preceding the publication of the Nuclear Safety and Radiation Protection Act 19 of 1995 (Act) by the Justice Ministry in 1995 (Justice, 1995) and the establishment of the Nigerian Nuclear Regulatory Authority (NNRA) in 2001, radioactive sources had for decades been used for various practices in Nigeria (Ogharandukun, 2017). These early activities involving radioactive sources gave rise to some legacy radioactive waste. NNRA undertook some early actions soon after its inception to ensure the safe management of this legacy radioactive waste. These actions, amongst other outcomes, highlighted the inadequacies of the Nigerian radioactive waste management system. The approval of radiation safety and radioactive waste management regulations enabled the NNRA to enter into national and international cooperative efforts to search for, secure, and create a proper inventory of the radioactive waste in Nigeria and effectively handle and manage it. Implementing the waste management system further highlighted the need for the approval of a national policy on radioactive waste management and the management of disused radioactive sources.

Implementing Lean 4.0: a review of case studies in pharmaceutical industry transformation

PurposeThe purpose of this systematic review is to critically analyze pharmaceutical industry case studies on the implementation of Lean 4.0 methodologies to synthesize key lessons, benefits and best practices. The goal is to inform decisions and guide investments in related technologies for enhancing quality, compliance, efficiency and responsiveness across production and supply chain processes.Design/methodology/approachThe article utilized a systematic literature review (SLR) methodology following five phases: formulating research questions, locating relevant articles, selecting and evaluating articles, analyzing and synthesizing findings and reporting results. The SLR aimed to critically analyze pharmaceutical industry case studies on Lean 4.0 implementation to synthesize key lessons, benefits and best practices.FindingsKey findings reveal recurrent efficiency gains, obstacles around legacy system integration and data governance as well as necessary operator training investments alongside technological upgrades. On average, quality assurance reliability improved by over 50%, while inventory waste declined by 57% based on quantified metrics across documented initiatives synthesizing robotics, sensors and analytics.Research limitations/implicationsAs a comprehensive literature review, findings depend on available documented implementations within the search period rather than direct case evaluations. Reporting bias may also skew toward more successful accounts.Practical implicationsSynthesized implementation patterns, performance outcomes and concealed pitfalls provide pharmaceutical leaders with an evidence-based reference guide aiding adoption strategy development, resource planning and workforce transitioning crucial for Lean 4.0 assimilation.Originality/valueThis systematic assessment of pharmaceutical Lean 4.0 adoption offers an unprecedented perspective into the real-world issues, dependencies and modifications necessary for successful integration, absent from conceptual projections or isolated case studies alone until now.

The Use of Big Data in Personalized Healthcare to Reduce Inventory Waste and Optimize Patient Treatment.

Precision medicine is emerging as an integral component in delivering care in the health system leading to better diagnosis and optimizing the treatment of patients. This growth is due to the new technologies in the data science field that have led to the ability to model complex diseases. Precision medicine is based on genomics and omics facilities that provide information about molecular proteins and biomarkers that could lead to discoveries for the treatment of patients suffering from various diseases. However, the main problems related to precision medicine are the ability to analyze, interpret, and integrate data. Hence, there is a lack of smooth transition from conventional to precision medicine. Therefore, this work reviews the limitations and discusses the benefits of overcoming them if big data tools are utilized and merged with precision medicine. The results from this review indicate that most of the literature focuses on the challenges rather than providing flexible solutions to adapt big data to precision medicine. As a result, this paper adds to the literature by proposing potential technical, educational, and infrastructural solutions in big data for a better transition to precision medicine.

Determination of driving power and dependency of wastes in the healthcare sector: a lean and ISM-Based approach

PurposeThe objective of this study is to systematically identify, categorize and assess the driving factors and interdependencies associated with various types of healthcare waste. The study specifically focuses on waste that has been managed or is recommended for treatment through the application of Lean Six Sigma (LSS) methodologies.Design/methodology/approachTo accomplish the study’s objectives, interpretive structural modeling (ISM) was utilized. This analytical tool aided in quantifying the driving power and dependencies of each form of healthcare waste, referred to as “enablers,” as well as their related variables. As a result, these enablers were classified into four distinct categories: autonomous, dependent, linkage and drivers or independents.FindingsIn the healthcare sector, the “high cost” (HC) emerges as an autonomous variable, operating with substantial independence. Conversely, variables such as skill wastage, poor service quality and low patient satisfaction are identified as dependent variables. These are distinguished by their low driving power and high dependency. On the flip side, variables related to transportation, production, processing and defect waste manifest strong driving forces and minimal dependencies, categorizing them as independent factors. Notably, inventory waste (IW) is highlighted as a salient issue within the healthcare domain, given its propensity to engender additional forms of waste.Research limitations/implicationsEmploying the ISM model, along with comprehensive case study analyses, provides a detailed framework for examining the complex hierarchies of waste existing within the healthcare sector. This methodological approach equips healthcare leaders with the tools to accurately pinpoint and eliminate unnecessary expenditures, thereby optimizing operational efficiency and enhancing patient satisfaction. Of particular significance, the study calls attention to the key role of IW, which often acts as a trigger for other forms of waste in the sector, thus identifying a crucial area requiring focused intervention and improvement.Originality/valueThis research reveals new insights into how waste variables are structured in healthcare, offering a useful guide for managers looking to make their waste-reduction strategies more efficient. These insights are highly relevant not just for healthcare providers but also for the administrators and researchers who are helping to shape the industry. Using the classification and ranking model developed in this study, healthcare organizations can more easily spot and address common types of waste. In addition, the model serves as a useful tool for practitioners, helping them gain a deeper, more detailed understanding of how different factors are connected in efforts to reduce waste.

First Generation Hazardous Waste Inventory for Developing A Master Plan for Hazardous Waste Management in Myanmar

Hazardous Waste Management (HWM) is an emerging priority in Myanmar, with the Environmental Conservation Department (ECD) under the Ministry of Natural Resources and Environmental Conservation (MONREC) acting as the nodal authority. Before the initiation of the HWM project in 2015, funded by the Norwegian government, Myanmar lacked essential regulations and statistical data concerning hazardous waste. The country formally ratified the Basel Convention in January 2015, mandating environmentally sound disposal of hazardous waste by its signatories. Crucial for effective waste management, hazardous waste generation information is fundamental for planning, implementation, and monitoring. Initial development stages involve the creation of first-generation inventories, which identify priority waste streams, sources, risks, and key stakeholders through basic calculations and management practice reviews. Myanmar's first-generation hazardous waste inventory, conducted from June 2016 to 2018, estimated that in 2017, approximately 280,600 tonnes/year of hazardous waste were generated, with projections foreseeing a 2.4-fold increase by 2030. Challenges in private industries, where waste streams, including hazardous waste, are often uncontrolled, led to underestimation of quantities. Data collection, however, employed cross-verification, site visits, and extensive consultations with the technical task force to enhance accuracy. This paper presents the purpose, methodology, major findings, and challenges faced during the formulation of Myanmar's first-generation hazardous waste inventory.

Pengendalian Kualitas Produk Menggunakan Lean Six Sigma dan Fuzzy FMEA Dalam Upaya Menekan Kecacatan Produk

Quality control is a process used to ensure the level of quality in a product or service so as to lead to customer satisfaction. UMKM Eko bubut is a UMKM that produces wooden handicrafts with product marketing that reaches the international market. In the problem of product quality control at UMKM Eko Bubut, it was found that there were five types of defects, namely wavy, rough, perforated, cracked, and broken defects. In addition, it was found that there was wastage that occurred which had an effect on disability. Solving quality control problems at UMKM Eko Bubut is by using lean six sigma to identify the sigma level and fuzzy FMEA is used to determine the main priority for repairs to the causes of production defects that occur. The results of the calculation of the defect level of bowl products, it was found that the types of defects were wavy (55.06%), rough (28.29%), perforated (7.82%), cracked (7.22%) and broken (1.61%). The identification results of the waste that occurs are waste defects (28.1%), waste overproduction (17.7%), waste waiting (16.2%), waste motion (16.0%), waste inventory (10.75%), waste transportation (6.55%), and over-processing (4.9%). The results of calculating the DPMO value obtained an average sigma of 3.27 with a DPMO value of 38890.41. This shows that for every 1,000,000 production, there is a possibility that there will be product defects in as many as 38,890 products. Factors that affect product defects are humans, raw materials, methods, machines, and the environment.

Wastewater Treatment Plant (WWTP) Bahagia Market on Kuala Dua Village Subdistrict Sungai Raya

Location of Bahagia Market on K.H. Abdurrahman Wahid streets, Kubu Raya regency. Bahagia Market has been operation for two years but doesn’t have wastewater treatment, the liquid waste product is discharged directly into the waters. The purpose of this plan is to knowing the discharge of wastewater generated, so the treatment is adjusted to the quality of wastewater and the available land area, as well as calculating cost budget. Planning methods is area survey, data collection, waste inventory, sampling, quality analysis, calculation of wastewater discharge, planning of wastewater treatment, and calculation of cost budget. The planning results are Bahagia market has 11 stalls, 64 loss and 43 tables with 3 drains. The liquid of wastewater come from the washing of vegetables, fish, meats, and poultry. BOD, COD, TSS, and ammonia parameters are above quality standards, while total coliform, fat and oil are below quality standards. Wastewater treatment project for the 5 next years starting from 2023 to 2027 with wastewater effluent is 8640 liters/days. Treatment unit use are sump well, bar screen, rotating biological contactor, settling basins, disinfection tub, and sludge drying bed with a land area of 5 m2 and a cost budget of Rp. 69,315,479.

A review on sustainable utilization of red mud based photocatalytic material for environmental pollution abetment

The inventory of the solid waste produced from Aluminium industries (Bauxite Residue) otherwise called red mud stands at an estimated amount of 4 billion tons globally owing to its current generation. So, to reduce the impact on environment, its safe disposal is posing a great threat to eco-friendly atmosphere and its utilization is must for environmental sustainability. High alkalinity nature and airborne dust emissions may posse threat to flora and fauna, but the mineral composition of red mud and red mud derived products found to be a promising material for the utilization in the field of environmental pollution remediation. The high content of largely inert components such as hematite that can be extracted and gives credibility to the idea that red mud can be used as a potential candidate in the field of photo catalysis. This review explores novel methods for treating red mud and extracting minerals, not only provide value to waste but also demonstrated reduced red mud can be used as effective catalyst in environmental abatement. Modification of red mud, extraction of valuable iron oxides creates a novel opportunity for efficient removal of toxic metals, dyes, inorganic and organic pollutants in the cost-effective method and maintains sustainability.

LOCAL GOVERNMENT POLICY IN EMPOWERING WOMEN IN HOUSEHOLD WASTE MANAGEMENT

Waste is the residue of human daily activities and natural processes in solid form. The waste production rate continues to increase, not only in line with population growth but also with the increasing consumption patterns of society. On the other hand, the waste management capacity conducted by both the community and local government still needs to be optimal. This research uses a normative juridical research method with a legal research approach. It employs standards using a literature review. The literature review in this research is based on legislation, books, journals, academic news media, and online sources. This research uses The legal approach to explore possible concepts and techniques. This normative legal research aims to find a general legal model for rationalizing natural resources. The Organic Village activities begin with meetings and planning within community groups at the Dasa Wisma level. In the Dasa-Wisma group meetings, a routine program is developed to conduct weekly organic and inorganic waste inventories. The challenges faced in the field are analyzed, and alternative solutions are considered. The Legok Makmur Organic Village activities start with meetings and planning within community groups at the Dasa Wisma level. The Legok Makmur activities carried out by the community association include daily organic waste counting, plant watering, processing of shredded organic waste every Sunday around noon, and receiving sales proceeds of inorganic waste from residents in exchange for goods. These topics include environmental maintenance, collaboration with club administrators, harvests, member shopping, external group members, vegetable cultivation, and poultry and fish farming. The community has the right and equal opportunity to think and actively participate in disaster management and environmental management.

Microbial Impacts on Colloid-Radionuclide Interactions

Microorganisms can play an important role on the behaviour of colloids in natural and engineered environments, which in turn can control the mobility of associated metals and radionuclides. This is especially true in the nuclear fuel cycle, where radionuclides (including uranium) can interact with a broad range of inorganic colloids. This is relevant to the legacy spent nuclear fuel ponds at Sellafield, which house a diverse inventory of waste from the early Magnox reactors. These reactors used uranium metal as a fuel encased in a magnesium non-oxide cladding. Corrosion of the cladding results in the release of radionuclides, primarily uranium, and the formation of brucite (Mg(OH)2) phases which are present both in the corroded Magnox sludge at the base of the pond and suspended in the water column as colloids (Gregson et al. 2011). These brucite colloids have the potential to mobilise insoluble phases providing an important pathway for radionuclide migration. The spent nuclear fuel ponds are maintained at high pH to minimise corrosion of the cladding, however significant corrosion has still occurred. Despite the seemingly inhospitable conditions in spent nuclear fuel ponds, numerous studies have found microorganisms capable of surviving in spent nuclear fuel ponds (Dekker et al. 2014, Foster et al. 2020, Ruiz-Lopez et al. 2020). Previous work has demonstrated increased abiotic sorption of strontium to brucite in the presence of organic matter derived from Pseudanabaena catenata (Ashworth et al. 2018), which dominates algal blooms in the ponds. In this study we focus on uranium interactions with colloidal brucite in the presence of microbes adapted to high pH environments under conditions relevant to the spent nuclear fuel ponds at Sellafield.

Controlling the Impact of Bentonite Microbial Communities in Disposal of Radioactive Wastes

Disposal in a geological disposal facility (GDF) is the preferred route for the world’s growing inventory of nuclear wastes. Bentonite clay is a common component of the engineered barrier system, serving to isolate and stabilise the high heat-generating waste packages in the geosphere (Stroes-Gascoyne et al. 2010). Bentonites naturally contain sulfate-reducing bacteria (SRB) (Haynes et al. 2021), which in the presence of the correct substrates, produce H2S that is highly corrosive to metals (such as steel waste packages). Sulfate, the electron acceptor, is present in most groundwaters, and the corrosion of steel produces hydrogen, an electron donor (Bagnoud et al. 2016). Compacting bentonite on deposition can restrict GDF microbial activity, since swelling pressures upon saturation restrict the available porosity for microbes (Masurat et al. 2010). Additionally, groundwater chemical conditions may impact bentonite mechanical properties (e.g., the effect of salinity on swelling capacity (He et al. 2019), and the energetics of bacterial metabolism (Oren 1999). This work uses bentonite SRB enrichment cultures to assess parameters that control microbial metabolism, and the relative contribution of microbially influenced corrosion (MIC), versus chemical corrosion of steel (Fig. 1). This will provide evidence to underpin lines of argument and models used in the safety assessments for geological disposal. Experiments described include microcosm incubations containing bentonite slurries across a range of salinity, and pressure cell bioreactors to evaluate the above conditions in the context of a compacted bentonite barrier system. Initial results show that in the presence of lactate as an electron donor, slurry systems with bentonite, low-carbon steel and sulfate-containing groundwater provide the essential nutrients for the proliferation of an MIC-inducing community (Fig. 2). Experiments have also shown that in such systems, increasing the groundwater NaCl concentration inhibits microbial activity during the 3-month experimental duration. Additionally, SRB have been shown to reduce priority radionuclides, such as selenium (Nancharaiah and Lens 2015). Selenium is a priority radionuclide in high-level waste, and in its highest oxidation states, selenate (Se(VI)) and selenite (Se(IV)), it is highly soluble and therefore mobile in the environment. Early experiments have shown that when an electron donor is present in microcosms containing bentonite and groundwater, bentonite-native SRB may be capable of reducing soluble selenium down to insoluble Se(0), restricting its environmental mobility.

Requirements for inventory models of radioactive waste

Abstract. The aim of the final disposal of radioactive waste is to ensure the best possible safety for the long-term protection (i.e. 1 million years) of humans and the environment from ionizing radiation and other harmful effects of this waste. In Germany, the Site Selection Act (StandAG) regulates the procedure for determining the site with the best possible safety for a repository with high-level radioactive waste. One of the mandatory aspects of the StandAG is to perform various preliminary safety assessments in order to assess the expected extent of the safe confinement of the radioactive waste. For this purpose, all information (in particular on the quantity, type, composition and activity) of the waste (i.e. the inventory) is required to conduct the respective safety assessment. On behalf of the Federal Office for the Safety of Nuclear Waste Management (BASE) and within the framework of the research project “Significance of the radioactive waste inventory in the site selection for a repository (InvEnd)”, Brenk Systemplanung GmbH identified the characteristics of the inventory required for the preliminary safety assessments. To determine these inventory characteristics, two main data sources were analysed, namely the generic but host-rock-specific concepts for a German high-level radioactive waste repository and the inventory data and approaches of other countries with technologically developed repository programmes. The identified characteristics can be divided into different groups (e.g. geometric, chemical, radiological and physical) and categories such as primary inventory data that are essential for carrying out the preliminary safety assessments or secondary inventory data which validate the primary inventory data. The evaluation of the impact of the identified characteristics shows that especially data on component-specific chemical composition and component-specific radionuclide inventory have a high impact on the results of safety assessments. These characteristics are, in turn, dependent on other characteristics, such as the irradiation history and the original chemical composition of the fuel in addition to the structural parts of the fuel assemblies. Furthermore, the study assesses uncertainties of the inventory characteristics, such as data uncertainty and conceptual uncertainty. The extent of data uncertainty depends on the inventory characteristic. However, in most cases, only qualitative assessments are possible. Conceptual uncertainties depend on the degree of simplification used to define reference wastes but cannot be quantified yet, as no reference wastes have been defined. The results of this study enable authorities and waste management organizations to identify the key data of high-level radioactive waste inventories that are essential for conducting safety assessments of repositories, even during early stages of site selection and planning.

International Atomic Energy Agency (IAEA) support for the management of site investigations for radioactive waste disposal facilities

Abstract. Providing safe, secure and environmentally acceptable radioactive waste disposal is a national responsibility that requires a long-term commitment, adequate resources and the involvement of multiple stakeholders. The choice of a particular disposal concept and its detailed design will depend on several factors, such as the properties of the waste inventory to be disposed of, national circumstances and strategic preferences. A concept is likely to evolve iteratively as one or more sites are investigated and the repository design is refined to reflect local conditions. In this context, the International Atomic Energy Agency (IAEA) recently published technical guidance on the management of site investigations for radioactive waste repositories. A key objective of the publication Management of Site Investigations for Radioactive Waste Disposal Facilities (IAEA, 2023) is to ensure that site investigation efforts in Member states have firm foundations based on a clear understanding of data and information requirements. The publication was developed to reflect the experiences and knowledge from a range of disposal programmes, and it is intended to support initiation of well-planned and focused site investigations in Member states with a need to develop and site radioactive waste disposal facilities. A siting process is intended to result in the identification of a suitable location for any nuclear installation, including a deep geological repository, and ultimately to receive authorisation to construct and operate the facility. To achieve this objective, it will be necessary to ensure that the combination of site properties and engineered barrier properties provides requisite levels of safety for the inventory under consideration (IAEA, 2015). The siting process and associated site investigations for a radioactive waste disposal facility follow a stepwise process, irrespective of whether the early stages of siting start with investigating and screening the national territory or whether the iterative investigation process starts with a more focused approach, e.g. volunteer sites, sites with already well-known characteristics, sites with existing nuclear facilities or similar ones (IAEA, 2023). Site investigations should follow a graded approach in an iterative manner, reflecting a phased approach to decision-making and the development of disposal facilities (IAEA, 2011). At each stage in the siting process the disposal system is to be evaluated based on the data and information available at that time. Following an assessment, a gap analysis comparing requirements to knowledge about the site would identify process model and data uncertainties affecting confidence in the implementation of the disposal concept at the site. Furthermore, the IAEA also recently launched a project to develop guidance reflecting good practices in Member states' programmes for establishing site selection criteria and applying a decision-making framework as part of a siting process.

Deep borehole disposal as a potential solution for high-level waste (HLW) and spent nuclear fuel (SNF) in Norway – current status and a first generic safety assessment

Abstract. Deep borehole disposal (DBD) is currently being investigated as a potential solution for the disposal of the existing spent nuclear fuel (SNF) in Norway. Over the past years, BGE TECHNOLOGY GmbH (BGE TEC), together with the Finnish companies A-Insinöörit Oy (AINS Group), Mitta Oy and VTT Technical Research, has supported the Norwegian agency Norwegian Nuclear Decommissioning (NND) in the development of a deep borehole concept, including work on different technical details. At the end of 2022, the consortium was able to win a follow-up contract to further deepen and advance the work. For this second framework agreement, additional companies were added to further strengthen the expertise. The Geological Survey of Finland (GTK), Posiva Solutions Oy (PSOY) and Rambøll are now part of the new consortium group, which works under the acronym GeoReN (Geological Repositories for Norway). This paper provides an overview of the work carried out in the past for the deep borehole concept in Norway. In detail, this includes a basic description of the concept developed for the waste that originates from different institutions. Initial calculations indicate that a 69 BSK-R canister may be sufficient for the waste inventory to be considered. As the current conceptual borehole design provides the basis for most of the other work carried out, it will be presented and discussed within the paper. Furthermore, as part of the concept development, a first generic post-closure safety assessment was also performed for the DBD concept. The main results of the long-term calculations are discussed and presented in this paper as well. The main objectives of the generic safety assessment were the identification of critical parameters and assumptions for the model of the DBD repository and the performance of a first assessment of possible consequences of the potential post-closure release of radionuclides from the borehole. To be able to give a prediction at the present stage of the project, the assessment used conservative assumptions, models and data. The preliminary results for the normal evolution of the deep borehole repository indicate that highly mobile radionuclides, such as I-129, Cl-36, Ni-59 and Se-79, are the major dose contributors and that the expected potential radiological impact on future generations associated with these releases is extremely small. In addition, alternative scenarios have been assessed, which assume a hydraulic gradient leading to advective flow either upward through the borehole and surrounding excavation damaged zone (EDZ) or between certain parts of the borehole and the surface via a transmissive fracture system. Despite the pessimistic assumptions chosen for these scenarios, the maximum dose rates are significantly lower than the expected regulatory limit. However, it needs to be pointed that the present generic safety assessment is still on a conceptual level. With more detailed planning and updated information regarding the inventory, the geological environment, and the integrity and performance of the engineered barriers, repeated safety assessments will need to be performed to derive more substantiated results.

Analisa Pemborosan Pada Proses Produksi Air Minum Dalam Kemasan Dengan Metode Value Stream Mapping Dan Waste Assesment Model Di CV Dafista Mulia

CV Dafista Mulia is a drinking water producer company located in Lamongan Regency. The problem that is often faced by companies is the amount of waste that occurs in the process of producing bottled drinking water. The most critical percentage of waste in the bottled water production process (AMDK) is waste overproduction with a weighting percentage of 25.4%; waste defet with a weighting percentage of 16.2%; waste inventory with a weighting percentage of 14.9%; waste unnecessary motion with a weighting percentage of 14.1%; waste transportation with a weighting percentage of 11.7%; waste waiting with a weighting percentage of 9%; and waste excess processing with a weighting percentage of 8.7%. The initial activity time before the repair was 466 minutes (7 Hours 46 Minutes) and after the repair was reduced to 416 minutes (6 Hours 51 Minutes). Based on the Failure Mode and Effect Analysis (FMEA), it is known that the root cause of the problem with the highest waste is Overproduction, namely production planning that is not quite right with a Risk Priority Number (RPN) score of 396. Recommendations for improvements that can be proposed are to carry out production planning using data - historical data that exists and is adjusted to balance the purchasing of raw materials with orders from consumers so that the results of the Overproduction can become a safety stock so that the Overproduction can function in the next consumer order.

Assessing the Scale of the Radioactive Waste Management Problem: A Review of European Union and International Reporting

Information on the management of radioactive waste (RW), including inventory, can be obtained from several sources, such as the International Atomic Energy Agency (IAEA) and the European Commission. The IAEA is collecting voluntary national profiles through the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The European Commission is requiring reports from Member States in accordance with Council Directive 2011/70/Euratom, which establishes a framework for the safe and responsible management of spent fuel and radioactive waste. The findings from these reports are published by the IAEA and EC every three years and provide comparable information on RW policies, frameworks, and programs, with a significant focus on waste and spent fuel inventories and associated practices and technologies. This paper reviews the latest available reports from the Commission and the IAEA, focusing on the RW inventory and disposal status. The paper presents some findings on the overall situation in the European Union (EU) and the comparison of inventories between EU Member States, as well as a comparison with the reporting from the IAEA regarding the global situation. The presentation of the radioactive waste and spent fuel inventories is normalized per person and land area, with the intention of improving understanding of the scale of the RW management problem. The relative scale of the problem is also demonstrated by comparison with hazardous waste inventories. There is a total of 264,000 tons of spent fuel worldwide, equivalent to concentration of 2 g/km2 or 0.04 g/capita. The total amount of all categories of radioactive waste is 37.6 million m3, equivalent to 290 l/km2 or 5 l/capita. The majority of RW (92%) is very low or low level, and 81% has already been disposed of. In comparison, ten times more hazardous waste is produced worldwide each year (~50 kg/capita/year). These numbers indicate that the amounts of RW are relatively small. The status reports, with a high percentage of RW disposed of, show that RW is routinely manageable, including the management of high-level RW. This is also demonstrated by the fact that Finland is soon to open a permanent disposal site, with several other countries following suit.