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Supply and demand in the ETS 2

The study looks at the functioning of the new emission trading system for road transport, buildings, and small installations (ETS 2) in the EU. It explains the rules governing the supply of allowances including the functioning of the market stability reserve (MSR) and the price containment mechanisms. Furthermore, it assesses the balance of supply and demand as well as auctioning revenues under different assumptions for the development of CO 2 emissions and CO 2 price. Finally, the interaction between the ETS 2 and national targets under the Effort Sharing Regulation (ESR) and the relationship with the German national ETS is assessed and an outlook for the period until 2040 is provided. Veröffentlicht in Climate Change | 09/2024.

Implementation and enforcement of EU regulations on fluorinated greenhouse gases (F-gases) und ozone-depleting substances (ODS) in Bulgaria

This report summarises the findings and results of the project “Implementation and enforcement of EU regulations on fluorinated greenhouse gases (F-gases) and ozone-depleting substances (ODS) in Bulgaria”. The project’s objective was to identify potential for improving the implementation and enforcement of different EU-regulations, e.g. of Regulation (EU) No. 517/2014, in Bulgaria. It focussed on the topics reporting, containment of ODS and F-gases, incentives for ODS destruction, supervision of the market (including internet trade), alternative technologies to F-gases, as well as training and certification contents and procedures addressing alternatives to F-gases. In addition to this final report, three guidance documents have been developed with more detailed information on the supervision of the market, on natural refrigerants, and on the training and certification topic. Veröffentlicht in Climate Change | 05/2017.

Long-term stability and leak tightness of reactor containments

Das Projekt "Long-term stability and leak tightness of reactor containments" wird vom Umweltbundesamt gefördert und von Zerna, Schnellenbach und Partner GmbH durchgeführt. Objective: the objective of this research is to study the long-term performance of structures comprising nuclear power plants. The time period of interest for this study is 140 years (this figure is based on maximum periods of 40 years for operation and 100 years of storage). Particular attention will be given to those parts of the plant for which leak tightness and structural integrity are required, both during operation and for long periods after final shutdown. This research will be executed in close cooperation with Taylor Woodrow construction ltd. The specific aim of this research is to investigate the behaviour of complex composite structures, taking as a basis the long-term behaviour of materials. The possible susceptibility to long-term damage will also be assessed, and the areas most prone to such damage will be identified. Further consideration will be given to the possible interaction between sealing steel components (steel containments, steel liners) and load bearing concrete structures. This building survey will be carried out on structural elements of actual pwr stations (e.g. Emsland-Lingen) and bwr stations (e.g. Gundremmingen b and c). Consideration will be given to the validity of the investigations for relevant structures of other commercial nuclear power plants in the European community. This investigation will include the shut-down bwr station of garigliano in Italy. General information: 1. Investigation on reinforced concrete and prestressed concrete structures. 1.1. Selection of structural elements considered important with regard to the integrity of long-term containment. 1.2. Literature study on material behaviour covering long-term properties. 1.3. Analysis of the long-term behaviour of the selected structural elements. 2. Investigation of steel containments. 2.1. Selection of elements susceptible to damage, in particular plastic sealings with concrete and steel. 2.2. Assessment of damage (state of material, types of corrosion, formation of condensed moisture, permeability of the concrete, etc.). 2.3. Optimization of ultrasonic testing techniques (angular sound, weakening, creep wave, etc.) And application of the selected techniques to decommissioned Niederaichbach and Gundremmingen i nuclear power plants. 3. Recommendations for monitoring and enhancing long-term integrity of reinforced and prestressed concrete and for assessment of in-situ corrosion of steel elements. Achievements: The main elements of reinforced concrete and prestressed concrete structures of reactor buildings were investigated concerning their long term performance, a period of about 100 years after decommissioning. As reference plants 2 German nuclear power plants were chosen, one pressurized water reactor (PWR) type and one boiling water reactor BWR type. A survey of the general long term behaviour of the structural elements, and especially of their components, concrete and reinforcement steel, was made. The development of strength and the ...

Schmelzen von radioaktivem Altmetall aus der KRB-A-Anlage

Das Projekt "Schmelzen von radioaktivem Altmetall aus der KRB-A-Anlage" wird vom Umweltbundesamt gefördert und von Kernkraftwerk RWE-Bayernwerk GmbH durchgeführt. Objective: radioactivity homogenisation and volume compaction of low-level radioactive scrap can be achieved by melting. Then, depending on the average specific activity, the metal can be released in general to the nuclear market, or stored for final disposal. However, melting in standard foundries without controlled containment atmosphere has to be limited to scrap with low specific activity (smaller than 74 bq/g), and large-scale experience with melting of higher-level radioactive metal scrap is presently not available. The work programme was, for technical and economic reasons, revised in a supplementary agreement concluded in 1988, after execution of items b.1. To b.2. The revision aims at gaining experience by large-scale melting of about 300 t of metal waste from the krb-a decommissioning, with radioactivity levels up to 500 bq/g. The melting will be performed in an induction furnace (capacity ca. 3t) in a controlled zone at the site of Siempelkamp Giesserei Krefeld (SRG), acting as subcontractor, the radioactive waste being transported from krb to SRG. The study is expected to result in a statement whether the above procedure has a potential for large-scale application. General information: b.1. Assessment of proposals for services from external contractors, mainly concerning the leasing of an induction melting furnace. B.2. Definition of a work procedure, including the selection of representative components for melting tests and of appropriate techniques for decontamination, dismouting and cutting, the definition of a procedure for the installation and operation of the melting furnace, and a preliminary planning for health physics protection. B.3. Preparation of licensing procedures for the installation and operation of a melting furnace on the site of SRG/Krefeld. B.4. Execution of the melting programme on the site of SRG/Krefeld. B.4.1. Conception and construction of a facility for the melting of metal scrap up to 500 bq/g. B.4.2. Study into the nuclide distribution during melting of contaminated and activated scrap. B.4.3. Nuclide-specific study into activity releases during two sequential melting processes. B.4.4. Casting of waste disposal packages containing higher-level radioactive (500 bq/g) components embedded in a matrix cast out of lower-level radioactive scrap ('onion package'). B.4.5. Melting of slag and sawing chips arising from dismantling processes. B.5. Evaluation of the above melting processes on the basis of laboratory analyses and conclusive assessment of the potential for large-scale application.

Vorhaben B3-8 - Entwicklung eines NGH-Carriers inkl. Containment-System

Das Projekt "Vorhaben B3-8 - Entwicklung eines NGH-Carriers inkl. Containment-System" wird vom Umweltbundesamt gefördert und von MEYER WERFT GmbH & Co. KG durchgeführt. Die Zielstellung des Teilvorhabens der MEYER WERFT ordnet sich der Zielstellung des Leitantrags des Konsortiums unter (siehe dort insbesondere 1.1, 1.2.3 und 2.4.2). Das Teilprojekt der MEYER WERFT ist eingebunden im Teilprojekt B3 'Gashydrattransport in Pelletform durch Nutzung anomal langsamer Zersetzung von Gashydraten'. Die Aufgabe der Entwicklung geeigneter Seetransportmittel unterteilt sich in die Untersuchungen zum Containment-System und der zugehörigen Transporteinheit. Die Lagerung/Fundamentierung (und Transporteinrichtungen) des Containment-Systems und Einrichtungen für die Ladungsaufnahme, sowie den internen Ladeguttransport/Stauung und Einrichtungen für eine Anlieferung des Ladegutes an entsprechende Abnahmeterminals an Land können nicht losgelöst von der Transporteinheit entwickelt werden und umgekehrt kann eine Entwicklung einer Transporteinheit nicht ohne spezifische Kenntnisse der Transportaufgabe entstehen. Da sich beide Entwicklungsprozesse gegenseitig sehr stark beeinflussen, kann ein sicher funktionierendes Transportmittel nur dann entwickelt werden, wenn bei der Grundauslegung (Basic Design) beides ganzheitlich betrachtet wird, hierzu gehören auch Aspekte der Sicherheit für Schiff und Umwelt. Aus diesem Grund findet unter anderem eine enge Interaktion mit dem Teilvorhaben B 3-5 'Sicherheitsevaluation und Gefahrenanalyse' statt. Diese ganzheitliche Betrachtung bereits im Basic Design bildet die Grundlage dafür, am Ende des Forschungsvorhabens ein durch die Klasse genehmigungsfähiges Transporteinheitskonzept zu erreichen.

330 MWE power plant with pressurized fluidized bed combustion and combined cycle gas and steam turbine (Design Stage)

Das Projekt "330 MWE power plant with pressurized fluidized bed combustion and combined cycle gas and steam turbine (Design Stage)" wird vom Umweltbundesamt gefördert und von Dawid-Saar durchgeführt. Objective: To design a 330 MWe demonstration power plant with pressurised fluidised bed combustion and combined cycle of gas and steam turbine. General Information: The project involves the complete design of a demonstration power plant, characterized by: - the combination of a pressurized fluidised bed firing system with a steam generator directly connected, a multi-shaft gas turbine plant and waste heat utilisation systems arranged downstream and integrated into the steam circuit for an electric power output of a total of approximately 330 MW. - very compact construction by means of a high pressure stage (16 bar) and housing of particularly critical heat-exposed components such as firing system, dust separator etc. in a spherical pressure containment. In addition to the recognized advantages of the fluidised bed firing system, such as: - considerable improvement of the emission characteristics due to the binding of noxious matter to a large extent - especially of SO2 - by the addition of absorbent directly into the fluidised bed, - drastically reduced nitrogen oxide and carbon monoxide formation as a result of low combustion temperatures and controlled combustion reaction. Further considerable advantages can be expected because of the complete plant design conceived in this case compared with conventional technology due to: - a marked increase in the degree of conversion of primary energy into electrical energy as compared with the usual hard coal fired power station with flue gas desulphurization plants from previously 38,6 per cent to 41,2 per cent, related to plant net power. - a reduction of the investment costs by 10-15 per cent with a simultaneously considerably reduced space requirement, a fact which is due in particular to the absence of flue gas desulphurization. - a considerable expansion of the fuel spectrum to include qualities containing large amounts of inerts and noxious matters (i.e. especially sulphur). - simple construction for flexible separation of heat. - significantly more compact design than AFBC. The total cost of the design phase, represented by this project, amounts to DM 10 million for which a 40 per cent subsidy has been granted.

Development of a floating lpg terminal based on a concrete barge with wet wall insulation of the storage compartments

Das Projekt "Development of a floating lpg terminal based on a concrete barge with wet wall insulation of the storage compartments" wird vom Umweltbundesamt gefördert und von LGA Gastechnik GmbH durchgeführt. Objective: Since the erection of land-based storage tanks for LPG in coastal terminals will face increasing difficulties (space requirements, safety consideration) it is the aim of the project to develop a storage unit which can be operated either floating in fore-shore areas or grounded at-shore. A mobile floating unit can be towed to the final site of operation, which, in many cases, may be an economical alternative to a fixed founded structure especially in regions with insufficient infrastructure. Another advantage is the fact that the whole equipment, including the reliquefaction plant and the storage tanks, can be installed at the construction site of the barge where all facilities are available in order to guarantee a high standard of fabrication. Once completed, the LPG terminal is towed to the location and anchored. General Information: The construction elements of the storage facility are concrete for the floating body and polyurethane foam for the insulation of the load bearing concrete walls of the containments. The special aspect of the project is the so-called wet wall insulation. Whilst the conventional insulation of low-temperature storage tanks is applied on the outside of the storage tank (and therefore not in contact with the liquid), a wet wall insulation shall be fitted inside the storage tank. This means that the insulation material is wetted by the stored liquid. Consequently, the effects of liquid/gas absorption, desorption, possible cracks and other defects have to be taken into account, when it comes to the selection of suitable PU foams. The target of the proposed development is to achieve a wet wall insulation consisting of: - a vapour barrier (liner) directly applied on the concrete walls - sprayed polyurethane foam built up in several layers - possibly reinforcement layers and/or LPG barriers incorporated in the PUF or applied into the PUF surface. The wet wall insulation will have the following main functions and characteristics: - thermal insulation to limit boil-off - a liquid barrier to prevent contact between concrete and cold LPG and to prevent LPG leakage - the vapour barrier prevents water vapour penetrating into the insulation - above functions must be fulfilled in a floating barge, in which the concrete barge as well as the LPG are to be considered as dynamic (liquid impact resistance) - insulation has to be load bearing. The development is aimed to achieve a technically acceptable and economically attractive floating LPG terminal. The wet wall insulation applied against the inner face of the barge's concrete compartments and in direct contact with the LPG is the essential part, because - it saves space and thus cost - it eliminates a double containment (e. g. insulated steel tanks placed inside or on a concrete barge). Achievements: CONCRETE BARGE: The design features of 2 types of storage barges, i.e. for the beached and floating version are available. For the beached storage barge, the results of ...

Modellentwicklung zu Vorgängen im Containment für das GRS-Codesystem AC2 (ATHLET / CD / COCOSYS)

Das Projekt "Modellentwicklung zu Vorgängen im Containment für das GRS-Codesystem AC2 (ATHLET / CD / COCOSYS)" wird vom Umweltbundesamt gefördert und von Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH durchgeführt. Im GRS-Codesystem AC2 werden Analysen zu Stör- oder Unfallabläufen in KKW zukünftig auf der Basis der nachfolgend genannten, gekoppelten Codes ermöglicht: 1) COCOSYS (Containment Code System) als detailliertes Analysewerkzeug für die Vorgänge im Sicherheitsbehälter (Containment); 2) ATHLET für die Vorgänge und Zustände im RDB bzw. im Primär- und Sekundärkühlkreislauf und 3) ATHLET-CD für die Phänomene bzw. für den Verlauf der Kernzerstörung im Reaktorkern bis hin zum Versagen des RDB und dem nachfolgenden Schmelzeaustrag ins Containment. Ziel dieses Vorhabens ist die Weiterentwicklung und Aktualisierung der Modelle für die Vorgänge im Sicherheitsbehälter in COCOSYS sowie die Arbeiten zur endgültigen Gestaltung der Kopplung zwischen COCOSYS und ATHLET/ATHLET-CD in AC2.

Demonstration of explosive dismantling techniques of the biological shield of the Niederaichbach nuclear power plant (KKN)

Das Projekt "Demonstration of explosive dismantling techniques of the biological shield of the Niederaichbach nuclear power plant (KKN)" wird vom Umweltbundesamt gefördert und von Battelle-Institut e.V. durchgeführt. Objective: This project aims at demonstrating explosive dismantling techniques on the biological shield of the nuclear power plant Niederaichbach (KKN), which was operated from 1972 to 1974 and is foreseen to be completely removed. The radioactive inventory of the shield is estimated in the order of 3.7E9 Bq (0.1 Ci). The level of activation is estimated to be in the order of 10 Bq/g, and the associated dose rates in the order of 10 micro Sv/h. Within this contract, blast peeling of the activated concrete from a 30C sector of the biological shield will be performed. This technique will be applied as one of 2 main techniques (hydraulic hammer besides blast peeling) for the dismantling of the whole biological shield of KKN; for this, the licensing authorities have already given their agreement. This demonstration project will be conducted according to the guidelines of the ongoing total dismantling of KKN. In particular, the generation of specific data on costs, working hours and job doses as well as on the amount of created secondary waste is considered as an important objective of this project. This will facilitate the application of this technology and acceptance from the safety point of view in future large-scale decommissioning operations. The project is a follow-up of small-scale work on inactive samples performed jointly under contracts FI1D0011 and FI1D0012. The work programme will be implemented jointly by three main contractors: Battelle Europe e.V./Frankfurt (BE), acting as coordinator, Noell/Würzburg (Noell) and Siemens/KWU (Siemens), as well as Stangenberg, Schnellenbach and Partner (SSP) as sub-contractor. Further cooperation is foreseen with TUV Bayern for the assessment of air filter systems. General Information: WORK PROGRAMME: 1. Preparatory planning and design work for on-site equipment and regulatory requirements (BE, Noell); 1.1. Layout of blasting patterns and of bore holes charging, according to the area of application (BE); 1.2. Design of blasting schemes according to the area of application (BE); 1.3. Definition of blasting area sub containments for the retention of dust, including associated filter systems (Noell, BE); 2. Demonstration blasting on the KKN shield by manual handling (BE, Noell); 2.1. Site preparation for the installation of tools and measuring devices (BE, Noell); 2.2. Assessment and implementation of auxiliary techniques such as bore hole drilling, cutting of the reinforcement by hydraulic shears, use of a hydraulic ram (Noell); 2.3. Main operation and concrete removal, consisting of a sequence of about 10 individual blasts, including pre- and post-blast working (BE, Noell); 2.4. Assessment of blasting performance, with respect to predetermined criteria such as concrete removal rate, safety aspects, integrated doses and generation of secondary waste (BE, Noell); 3. Assessment of dust retention by industrial filter systems with respect to efficiency and safety of handling (Noell, BE); 4. Assessment of ...

Barrier performance of cements and concretes in nuclear waste repositories

Das Projekt "Barrier performance of cements and concretes in nuclear waste repositories" wird vom Umweltbundesamt gefördert und von Forschungszentrum Jülich GmbH, Institut für Sicherheitsforschung und Reaktortechnik durchgeführt. General Information: Cement barriers have been demonstrated to provide physical and chemical containment of nuclear waste. The problem has been to verify the mechanistic basis of their performance now and in the future. The project aims at unifying practical and theoretical approaches to performance testing and prediction The fundamental science of immobilisation will be developed by enhancing computer-based models of chemical behaviour and linking chemical models with physical models of transport properties of permeable materials and of cracked barriers. Modest data base expansion will be undertaken. Test methods will be developed which realistically accelerate degradation of cements in a range of natural environments. These test methods will be applied to a range of inactive simulants as well as active wastes. Furthermore, they will be closely linked with field trials at Mol and with the computer-based simulations described above. The inactive components of radioactive waste streams may interfere with performance. Consequently, the impact of waste stream constituents such as flocs upon leach properties and performance will be determined. Inactive simulant and active cemented waste samples will be tested at Mol using oxidised and fresh (reduced) clay. These realistic tests will parallel accelerated laboratory leach and modelling predictions, the three sets of results from computer modelling, from accelerated tests and from actual exposure will be critically compared and evaluated. The range of temperatures will be 20-85 C and groundwater compositions range from pure to saline. The Mol pure water composition will provide an important benchmark. The methodology used throughout will be standard but state-of-the-art. The participants have all had extensive experience in the field and, in many instances, will have worked together in the course of previous EC programmes. The coordinator will work with partners to ensure the best possible sharing of experience to enhance the value of the project to the Community and its member states. Prime Contractor: University of Aberdeen, Department of Chemistry; Aberdeen; United Kingdom.

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