scholarly journals SITE SELECTION OF A GEOLOGICAL REPOSITORY FOR THE SAFE DISPOSAL OF HIGH-LEVEL WASTE IN THE STATE OF RIO DE JANEIRO

2015 ◽  
Vol 5 (1) ◽  
Author(s):  
Corbiniano Silva ◽  
Monica Da Costa Pereira Lavalle Heilbron ◽  
Paulo Fernando Lavalle Heilbron Filho
Keyword(s):  
Site Selection ◽  
Rio De Janeiro ◽  
The State ◽  
High Level Waste ◽  
Safe Disposal ◽  
Geological Repository ◽  
High Level ◽  
Selection Of

scholarly journals Selection of a tool to decision making for site selection for high level waste

2016 ◽  
Vol 2 ◽  
pp. 6
Author(s):  
Jonni Guiller Madeira ◽  
Antônio Carlos M. Alvim ◽  
Vivian B. Martins ◽  
Nilton A. Monteiro
Keyword(s):  
Decision Making ◽  
Site Selection ◽  
High Level Waste ◽  
Selection For ◽  
High Level ◽  
Selection Of

The fixation of high-level wastes in glasses

1986 ◽  
Vol 319 (1545) ◽  
pp. 49-62 ◽  
Keyword(s):  
Borosilicate Glass ◽  
High Level Waste ◽  
Geological Repository ◽  
Important Barrier ◽  
Processing Wastes ◽  
Under Construction ◽  
High Level ◽  
Thermal Stability Of ◽  
Selection Of

A plant for the fixation of high-level wastes in borosilicate glass has been operating in France since 1978. A large plant is under construction in the U.S. for the fixation of defence high-level waste and plans for other glass fixation plants are well advanced at several sites around the world. Among the reasons for the selection of borosilicate glass as a fixation medium are the relative ease of processing wastes of variable composition by means of well established technology, and the long-term radiation and thermal stability of the glass. Well formulated glass also has sufficient resistance to the action of groundwater so that it can serve as an important barrier against the spread of radionuclides via groundwater in any forseeable situation. Research is continuing to quantify the reactions of waste glass in site-specific geological repository environments.

GIS Based Multi-Criteria decision support system and machine learning for Hospital Site Selection case study Oran - Algeria

2022 ◽  
Vol 14 (1) ◽  
pp. 0-0
Keyword(s):  
Site Selection ◽  
Decision Makers ◽  
Analysis Method ◽  
Automatic Learning ◽  
Hospital Site ◽  
Set Up ◽  
High Level ◽  
Selection Of ◽  
The Ideal

The selection of hospital sites is one of the most important choice a decision maker has to take so as to resist the pandemic. The decision may considerably affect the outbreak transmission in terms of efficiency , budget, etc. The main targeted objective of this study is to find the ideal location where to set up a hospital in the willaya of Oran Alg. For this reason, we have used a geographic information system coupled to the multi-criteria analysis method AHP in order to evaluate diverse criteria of physiological positioning , environmental and economical. Another objective of this study is to evaluate the advanced techniques of the automatic learning . the method of the random forest (RF) for the patterning of the hospital site selection in the willaya of Oran. The result of our study may be useful to decision makers to know the suitability of the sites as it provides a high level of confidence and consequently accelerate the power to control the COVID19 pandemic.

scholarly journals Corrosion of carbon steel components in the French high-level waste programme: evolution of disposal concept and selection of materials

2017 ◽  
Vol 52 (sup1) ◽  
pp. 17-24 ◽  
Author(s):  
Didier Crusset ◽  
Valérie Deydier ◽  
Sophia Necib ◽  
Jean-Marie Gras ◽  
Pierre Combrade ◽  
...  
Keyword(s):  
Carbon Steel ◽  
High Level Waste ◽  
High Level ◽  
Selection Of

CAREM X INPRO Case Study

2004 ◽  
Author(s):  
Pablo C. Florido ◽  
Dari´o Delmastro ◽  
Daniel Brasnarof ◽  
Osvaldo E. Azpitarte
Keyword(s):  
Nuclear Reactor ◽  
Fuel Cycle ◽  
High Level Waste ◽  
Fuel Cycles ◽  
Surface Intermediate ◽  
Geological Repository ◽  
Enriched Uranium ◽  
Intermediate Storage ◽  
High Level

Argentina is performing CAREM X Nuclear System Case Study based on CAREM nuclear reactor and Once Through Fuel Cycle, using SIGMA for enriched uranium production, and a deep geological repository for final disposal of high level waste after surface intermediate storage in horizontal natural convection silos, to verify INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles) methodology. Projections show that developing countries could play a crucial role in the deployment of nuclear energy, in the next fifty years. This case study will be highly useful for checking INPRO methodology for this scenario. In this contribution to ICONE 12, the preliminary findings of the Case Study are presented, including proposals to improve the INPRO methodology.

scholarly journals Reactive transport calculations to evaluate sulphide fluxes in the near-field of a SF/HLW repository

2019 ◽  
Vol 98 ◽  
pp. 10005
Author(s):  
Marek Pękala ◽  
Paul Wersin ◽  
Veerle Cloet ◽  
Nikitas Diomidis
Keyword(s):  
Reactive Transport ◽  
Spent Nuclear Fuel ◽  
Near Field ◽  
Opalinus Clay ◽  
High Level Waste ◽  
Waste Containment ◽  
Geological Repository ◽  
High Level ◽  
Reducing Bacteria ◽  
Hlw Repository

Radioactive waste is planned to be disposed in a deep geological repository in the Opalinus Clay (OPA) rock formation in Switzerland. Cu coating of the steel disposal canister is considered as potential a measure to ensure complete waste containment of spent nuclear fuel (SF) and vitrified high-level waste (HLW) or a period of 100,000 years. Sulphide is a potential corroding agent to Cu under reducing redox conditions. Background dissolved sulphide concentrations in pristine OPA are low, likely controlled by equilibrium with pyrite. At such concentrations, sulphide-assisted corrosion of Cu would be negligible. However, the possibility exists that sulphate reducing bacteria (SRB) might thrive at discrete locations of the repository’s near-field. The activity of SRB might then lead to significantly higher dissolved sulphide concentrations. The objective of this work is to employ reactive transport calculations to evaluate sulphide fluxes in the near-field of the SF/HLW repository in the OPA. Cu canister corrosion due to sulphide fluxes is also simplistically evaluated.

scholarly journals State-of-the-art and proof-of-concept installations for repository concepts based in crystalline rock

2015 ◽  
Vol 79 (6) ◽  
pp. 1665-1673 ◽  
Author(s):  
Magnus Kronberg ◽  
Jan Gugala ◽  
Keijo Haapala
Keyword(s):  
Laser Scanning ◽  
Crystalline Rock ◽  
High Level Waste ◽  
Geological Disposal ◽  
Geological Repository ◽  
Reference Design ◽  
Potential Alternative ◽  
Deep Underground ◽  
High Level

AbstractOver the last five decades private and national energy programmes worldwide have been producing a variety of radioactive wastes. One of the safest ways of disposing of this waste is to bury it deep underground in purpose-built geological disposal facilities. Currently, there is no operating geological repository in Europe for high-level waste but the goal of the IGD-TP is that the first repository shall be fully operational before the year 2025. Several studies and experiments are ongoing at various potential repository sites in Europe with the goal to establish general approaches that can be adapted for any country in need of a geological repository.The Swedish Nuclear Fuel and Waste Management Co (SKB) in Sweden and Posiva Oy in Finland are developing a method for geological disposal of high-level long-lived nuclear waste in crystalline rock, the KBS-3 method. KBS-3V (vertical) is both organizations reference design, but KBS-3H (horizontal) emplacement is also being researched as a potential alternative. Of high importance in the development is demonstrating the technical feasibilityin situof safe and reliable construction, manufacturing, disposal and sealing of such geological disposal facilities. Parts of these demonstrations are carried out under the framework of EurAtom/FP7 and one of these projects is the LUCOEX project where SKB is demonstrating horizontal emplacement, the Multi Purpose Test (MPT), and Posiva is demonstrating vertical buffer installation processes.The MPT includes the key components of the horizontal design and comprises all essential steps; manufacturing of the full-scale components, their assembly, installation in the drift and monitoring of the early buffer evolution. The MPT installation was successfully performed in late 2013. By combining the components, an initial verification of the design implementation has been achieved. At the same time, integrating the components has meant the recognition of some design weaknesses and the design will be updated accordingly.Posiva's KBS-3V buffer installation equipment that places buffer blocks with high precision in vertical deposition holes is currently being developed and will be tested during 2014 and 2015 in real underground conditions. The machine uses vacuum lifting tools for moving the buffer blocks and laser scanning technology to position both the machine and blocks. Functionality of the concept and equipment selected will be confirmed by the tests and the installation tests will provide important information about the suitability of the selected buffer dimensions and tolerances.

Nuclear reactor high-level waste: Origin and safe disposal

1991 ◽  
Vol 32 (1) ◽  
pp. 1-9
Author(s):  
Christopher Chua ◽  
Kosta Tsipis
Keyword(s):  
Nuclear Reactor ◽  
High Level Waste ◽  
Safe Disposal ◽  
High Level
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