Technologies for the containment, immobilization, and disposal of radioactive wastes

1989 ◽  
Vol 16 (4) ◽  
pp. 444-458 ◽  
Author(s):  
J. C. Tait ◽  
P. J. Hayward ◽  
J. S. Devgun
Keyword(s):  
Electrical Power ◽  
Radioactive Wastes ◽  
Radioactive Isotopes ◽  
High Level Waste ◽  
Technical Aspects ◽  
Geological Disposal ◽  
Low Level ◽  
High Level ◽  
Nuclear Fuel Waste ◽  
Canada Limited

Atomic Energy of Canada Limited is developing methods for the management and safe disposal of radioactive wastes. These wastes range from the highly radioactive (high-level) UO2 fuel arising from the nuclear generation of electrical power to the low- and intermediate-level wastes arising from research in various Canadian institutions using radioactive isotopes. This paper reviews the current research programs on materials and processes for the immobilization and containment of UO2 fuel wastes and the technical aspects of programs demonstrating the various technologies needed for implementing a disposal program for low-level wastes. Key words: waste management, radioactive, nuclear fuel waste, high-level waste, low-level waste, disposal, immobilization, glass, containment, siting, land burial, geological disposal.

Geological Disposal for High-Level Waste: Ethical Considerations

2001 ◽  
Author(s):  
Gustaaf C. Cornelis
Keyword(s):  
Time Scales ◽  
Waste Disposal ◽  
High Level Waste ◽  
Ethical Considerations ◽  
Technical Aspects ◽  
Geological Disposal ◽  
High Level

Abstract This paper describes the activities launched at SCK•CEN, intended to explore ethical and other non-technical aspects when dealing with the time scales considered in the high-level waste disposal program. (1) Especially the issues of retrievability and precaution will be focused on philosophically. Many questions will be raised in order to sensitize all stakeholders for the transdisciplinary character of the transgenerational problem at hand.

The Belgian R&D Feasibility Programme on the Geological Disposal of High-Level and Long-Lived Radioactive Waste

2013 ◽  
Author(s):  
Philippe Van Marcke ◽  
William Wacquier
Keyword(s):  
Radioactive Waste ◽  
High Level Waste ◽  
Reference Solution ◽  
Conceptual Level ◽  
Geological Disposal ◽  
Low Level ◽  
High Level ◽  
Term Management

ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, considers geological disposal in poorly indurated clay as the reference solution for the long-term management of high-level waste (HLW) and intermediate and low level waste, long-lived (ILLW-LL). The disposal concept entails the post-conditioning of the waste in disposal packages and the subsequent disposal of these packages in an underground repository. The R&D feasibility programme on geological disposal aims at demonstrating, at a conceptual level, that the proposed disposal system can be constructed, operated and closed.

Performance Assessment of a High-Level-Waste Repository in Clay

1988 ◽  
Vol 127 ◽  
Author(s):  
Jan L. Marivoet ◽  
Geert Volckaert ◽  
Arnold A. Bonne
Keyword(s):  
Performance Assessment ◽  
Maximum Dose ◽  
High Level Waste ◽  
Clay Layer ◽  
Geological Disposal ◽  
Dose Rates ◽  
Consequence Analysis ◽  
Calculated Dose ◽  
Order Of Magnitude ◽  
High Level

ABSTRACTPerformance assessment studies have been undertaken on the geological disposal of high-level waste in a clay layer in the framework of the CEC project PAGIS. The methodology applied consists of two consecutive steps : a scenario and a consequence analysis. The scenario analysis has indicated that scenarios of normal evolution, of human intrusion, of climatic change, of secondary glaciation effects and of faulting should be evaluated. For the consequence analysis as well deterministic “best estimate” as stochastic calculations, including uncertainty, risk and sensitivity analyses, have been elaborated.The calculations performed show that most radionuclides decay to negligible levels within the first fewjneters of the clay barrier. Just a few radionuclides, 99Tc, 135Cs and 237Np with its daughter nuclides 233U and 229Th can eventually reach the biosphere. The maximum dose rates arising from the geological disposal of HLW, as evaluated by the “best-estimate” approach are about 10−11 Sv/y for river pathways. If the sinking of a water well into the 150 m deep aquifer layer in the vicinity of the repository is considered together with a climatic change, the maximum calculated dose rate rises to a value of 3×10−7 Sv/y. The maximum dose rates evaluated by stochastic calculations are about one order of magnitude higher due to the considerable uncertainties in the model parameters. In the case of the Boom clay the estimated consequences of a fault scenario are of the same order of magnitude as the results obtained for the normal evolution scenario. The maximum risk is estimated from the results obtained through stochastic calculations to be about 5×10−8 per year. The sensitivity analysis has shown that the effective thickness of the clay layer, the retention factors of Tc, Cs and Np, and the Darcy velocity in the aquifer are parameters which strongly influence the calculated dose rates.

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.

Evaluation of Long-Term Irradiation Field in Geological Disposal of High-Level Radioactive Wastes

2000 ◽  
Vol 37 (sup1) ◽  
pp. 310-315
Author(s):  
H Sawamura ◽  
K Nishimura ◽  
M Naito ◽  
T Ohi ◽  
Y Ishihara ◽  
...  
Keyword(s):  
Radioactive Wastes ◽  
Geological Disposal ◽  
Irradiation Field ◽  
High Level

High-level Waste, Low-level Logic

1994 ◽  
Vol 50 (6) ◽  
pp. 40-45
Author(s):  
Kristin Shrader-Frechette
Keyword(s):  
High Level Waste ◽  
Low Level ◽  
High Level

scholarly journals EFFECT OF COUPLING BEHAVIOR ON GROUNDWATER FLOW FOR GEOLOGICAL DISPOSAL OF RADIOACTIVE HIGH LEVEL WASTE

2003 ◽  
pp. 261-271
Author(s):  
Hiroshi KURIKAMI ◽  
Akira KOBAYASHI ◽  
Masakazu CHIJIMATSU ◽  
Yuzo OHNISHI
Keyword(s):  
Groundwater Flow ◽  
High Level Waste ◽  
Geological Disposal ◽  
Coupling Behavior ◽  
High Level
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