final disposal
Recently Published Documents


TOTAL DOCUMENTS

356
(FIVE YEARS 96)

H-INDEX

14
(FIVE YEARS 2)

RSC Advances ◽  
2022 ◽  
Vol 12 (3) ◽  
pp. 1813-1833
Author(s):  
Tariq Almubarak ◽  
Jun Hong Ng ◽  
Raja Ramanathan ◽  
Hisham A. Nasr-El-Din

In this review, we discuss how chelating agents and their products can cause corrosion and how it goes through the oilfield cycle including thermal, photo, and biodegradation.


2021 ◽  
Vol 5 (6) ◽  
pp. 1500-1506
Author(s):  
Ambar Tri Ratnaningsih ◽  
David Setiawan ◽  
Latifa Siswati

Inorganic waste is a type of waste that is difficult to decompose naturally by microorganisms. Inorganic waste processing is carried out by collecting, disposing and transporting it to the final disposal site (TPA). There needs to be an effort to utilize inorganic waste, especially plastics, into useful products. People in Limbungan Village, Rumbai Pesisir District, Pekanbaru City already have a waste bank, but the benefits have not been felt by the community because inorganic waste is still being disposed of. There is a need for efforts to socialize and educate the public to process inorganic waste into handicraft products that have economic value. The method is carried out by educating the public about waste processing in general and demonstrating the use of plastic waste into handicraft products. After the counseling was carried out, the community had knowledge about waste management in general and skills in processing plastic waste into handicraft products such as bags, candy containers that were suitable for use and worthy of sale


Energies ◽  
2021 ◽  
Vol 14 (24) ◽  
pp. 8459
Author(s):  
Gabriele Di Giacomo

While receiving nearly 10,000 times the energy that we presently need from the Sun, almost 600 EJ/a, developed and developing countries continue to mostly use fossil fuels even though the technologies available and the adaptation of individual and collective behaviours could make it possible to use only solar energy [...]


2021 ◽  
Vol 13 (2) ◽  
pp. 88-99
Author(s):  
Bruce Wellington Amorin da Silva ◽  
Márcio Roberto Duran Filho ◽  
Luana Inada Souza Santos ◽  
Beatriz Leite ◽  
Douglas Liberace de Matos

Brazil is the largest sugar and alcohol producer in the world, consequently, it is also a major vinasse producer, which is a problem, as it has a high potential for pollution, severely impacting the soil and water, despite being used in fertigation of cane fields. When treated in anaerobic conditions, however, it can produce energy and be used as a biofertilizer for the soil. This treatment can be performed by an Upflow Anaerobic Sludge Blanket (UASB), considered efficient by the literature. Based on this, this article tries to gather equations and collect data, reviewing the scientific literature with the objective of designing an UASB for the treatment of vinasse, exposing an alternative of suitable final disposal for this by-product. The results show good opportunities, with a great potential for reducing BOD and COD and producing biogas, electricity and biofertilizer, in addition to providing a compilation of equations and important data for future calculations.


Author(s):  
Suwati Ummat ◽  
Marianah Marianah ◽  
Muanah Muanah ◽  
Ahmad Akromul Huda ◽  
Desy Ambar Sari ◽  
...  

Household waste contributes to the volume of waste. In general, household waste is easily biodegradable and difficult to decompose. Household products that are hard to decompose are generally plastic and plastic bottles predominantly. The difficulty of decomposing household plastic waste requires serious handling, so it is necessary to provide assistance for processing plastic waste into useful creations. One of them becomes ecobric. There are two methods of this activity, namely direct counseling and training. The results obtained after the community service activities were completed was that they were able to improve community skills in processing plastic waste into ecobrics. Furthermore, ecobrics are created into potted plants and other forms of creation. In addition, after this activity is carried out, it can reduce the movement of plastic waste to the final disposal site (TPA), so that the community hopes that this activity will continue to be transmitted to other places to create a clean and free environment from plastic waste.


2021 ◽  
Vol 1 ◽  
pp. 99-100
Author(s):  
Ute Maurer-Rurack ◽  
Guido Bracke ◽  
Eva Hartwig-Thurat ◽  
Artur Meleshyn ◽  
Torben Weyand

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


2021 ◽  
Vol 1 ◽  
pp. 241-242
Author(s):  
Irmgard Niemeyer ◽  
Katharina Aymanns ◽  
Guido Deissmann ◽  
Dirk Bosbach

Abstract. The objectives of international safeguards are the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons (or for other purposes), and deterrence of such diversion by the risk of early detection for states with comprehensive safeguards agreements with the International Atomic Energy Agency (IAEA). Following these objectives, several studies have focused on the developments of concepts and methods for safeguarding final disposal facilities as well as on identifying the most feasible technologies that could potentially be deployed for verifying final disposal programmes (IAEA, 1998, 2010, 2018). These activities were coordinated through Member State Safeguards Support Programmes, including the joint tasks on the development of “Safeguards for Geological Repositories” (SAGOR, 1994–2004) and on the “Application of Safeguards to Geological Repositories” (ASTOR, 2005–2017). SAGOR performed a diversion path analysis for spent fuel disposal facilities, determined safeguards technical objectives and identified potential safeguards measures to meet those objectives. ASTOR supported the IAEA in assessing how safeguards measures could be effectively implemented and provided recommendations with respect to developing such measures. Specific verification technologies were developed under other Member State Support Programme tasks. A summary report on the progress and status of safeguards for spent fuel encapsulation plants and geological repositories was completed by ASTOR in 2017. ASTOR also identified areas and actions that need to be accomplished to support safeguards implementation in final disposal facilities, such as (1) establish performance requirements for the design of safeguards technologies relevant to geological disposal of spent fuel, (2) determine specific information needs of states and operators regarding safeguards implementation for geological disposal of spent fuel and develop appropriate guidance, (3) determine specific information needs of IAEA inspectors and analysts and develop a guidance document that provides recommendations for implementing safeguards for a geological repository system under the state-level concept and (4) develop and test appropriate safeguards equipment (IAEA, 2017; Moran et al., 2018). While several measures and technologies related to verifying the geological disposal of spent fuel have been used by the IAEA at other facilities or are in development or testing, other technologies still need to be developed and tested. In addition, ASTOR identified the need for approaches to how information about disposed spent fuel and high-level nuclear waste should be managed, handled, organized, archived, read, interpreted and secured for the long term (for centuries after repository closure and beyond), including an international standard for states and facility operators on information management, data-retention methods and timescales for preserving safeguards data for geological repositories. The presentation will introduce the objectives of international nuclear material safeguards for the final disposal of spent nuclear fuel, highlight the current status of developments and discussions in terms of approaches and technologies for safeguarding geological repositories, and give an outlook on implementing safeguards for final disposal in Germany.


2021 ◽  
Vol 1 ◽  
pp. 13-14
Author(s):  
Efstathios Vlassopoulos ◽  
Susanne Pudollek ◽  
Olympios Alifieris ◽  
Dimitrios Papaioannou ◽  
Ramil Nasyrow ◽  
...  

Abstract. Radioactive waste in Switzerland will be disposed of in a deep geological repository (DGR). Responsible for the planning and preparation of realization of this task is National Cooperative for the Disposal of Radioactive Waste (Nagra). Spent fuel assemblies (SFA) constitute the main high-level waste (HLW) stream that will be disposed in the DGR. Prior to final disposal they will be transferred or transported to an encapsulation plant, where they will be loaded into final disposal canisters. To ensure that the structural integrity of SFAs is not compromised during handling and transportation, it is desirable to characterize the expected mechanical parameters of SFAs after long-term interim storage. Experimental research activities performed at the JRC Karlsruhe include safety aspects of radioactive waste management, encompassing also spent fuel storage and spent fuel/HLW disposal activities. Nagra and JRC have established a collaboration to jointly study relevant properties and behaviours of spent fuel rods, with the support of the Gösgen nuclear power plant and of Framatome, and in collaboration with other partners in Europe and internationally. As part of this collaboration, 3-point bending and impact tests were performed at the hot-cell facilities of JRC Karlsruhe, to determine the mechanical response of spent fuel rodlets under quasi-static and dynamic loads. The structural integrity of fuel rods was also evaluated under different handling scenarios using finite element (FE) analysis. Starting with the construction of a static 3D FE model of a Pressurized Water Reactor (PWR) nuclear fuel rodlet in ANSYS Mechanical, Nagra has developed a series of FE models over the years. Mechanical properties of the original rodlet model were derived through an extensive validation process, using experimental data from the 3-point bending tests. To evaluate the mechanical response of an SFA in different loading scenarios, this model was expanded using 1D beam modeling approach. The development of the simplified 1D models is shown in this presentation. In particular, the effect of the contact formulation between the spacer grid and the rods is discussed. Finally, preliminary results of the bending response of a 15×15 PWR SFA sub-model are presented.


2021 ◽  
Vol 1 ◽  
pp. 259-260
Author(s):  
Matthias Englert ◽  
Simone Mohr ◽  
Saleem Chaudry ◽  
Stephan Kurth

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


Sign in / Sign up

Export Citation Format

Share Document