Preliminary Post-Emplacement Safety Analysis of the Subseabed Disposal of High-Level Radioactive Waste

1983 ◽  
Vol 26 ◽  
Author(s):  
Maureen F. Kaplan ◽  
Charles M. Koplik
Keyword(s):  
Radioactive Waste ◽  
Nuclear Waste ◽  
North Pacific ◽  
Sensitivity Analyses ◽  
Radionuclide Transport ◽  
Radiological Hazard ◽  
Systems Model ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Central North Pacific

ABSTRACTThe radiological hazard from the disposal of high-level nuclear waste deep within the ocean sediments is evaluated, on a preliminary basis, for locations in the central North Pacific and in the northwestern Atlantic. Radionuclide transport in the sediment and water column and by marine organisms is considered. Peak doses to an individual are approximately five orders of magnitude below background levels for both places. Sensitivity analyses for several imporLant aspects of the post-emplacement systems model are described.

Radionuclide Transport Modelling in Fissured Zones and Channels

1985 ◽  
Vol 50 ◽  
Author(s):  
Anders Rasmuson ◽  
Ivars Neretnieks
Keyword(s):  
Velocity Field ◽  
Nuclear Waste ◽  
Exact Analytical Solution ◽  
Crystalline Rock ◽  
Water Velocity ◽  
Flowing Water ◽  
Radionuclide Transport ◽  
Transport Modelling ◽  
High Level Nuclear Waste ◽  
High Level

AbstractRadionuclides escaping from a repository for high level nuclear waste in crystalline rock may eventually be carried by the flowing water in fissure zones. In such zones the rock is broken in blocks of varying sizes and shapes. Also, the water velocity may vary very much along the flow path. The integrated finite difference method (IFDM) is proposed for numerical calculations of radionuclide transport in such zones. A method for lumping blocks of various sizes and shapes into a single PSEUDOBODY is tested by comparing it with an exact analytical solution which can account for the diffusion into blocks of any size distribution. The errors obtained in using the PSEUDOBODY-approach are found to be small. Furthermore, a method for determining an “average” Peclet number in a strongly varying velocity field is tested and found to give comparatively small errors.

Chemical structure and dissolution behaviour of CaO and ZnO containing alkali-borosilicate glass

2022 ◽  
Author(s):  
Adam J Fisher ◽  
Hao Ding ◽  
Prashant Rajbhandari ◽  
Brant Walkley ◽  
Lewis R Blackburn ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Chemical Structure ◽  
Sodium Borosilicate Glass ◽  
Waste Vitrification ◽  
Dissolution Behaviour ◽  
High Level Nuclear Waste ◽  
High Level

Within the context of the UK’s radioactive waste vitrification programme, which utilises a lithium-sodium borosilicate glass modified with CaO and ZnO to immobilise high level nuclear waste, an investigation was...

The Geomicrobiology of Nuclear Waste Disposal

1983 ◽  
Vol 26 ◽  
Author(s):  
Julia M. West ◽  
Ian G. McKinley
Keyword(s):  
Waste Management ◽  
Nuclear Waste ◽  
Waste Disposal ◽  
Microbial Contamination ◽  
Nuclear Waste Disposal ◽  
Nuclear Waste Management ◽  
Radionuclide Transport ◽  
High Level Nuclear Waste ◽  
The Uk ◽  
High Level

ABSTRACTThe geomicrobiology of high-level nuclear waste disposal is a new field in the area of nuclear waste management. Until recently the likelihood of microbial contamination in a deep repository had not been considered, but possible biogeochemical effects of repository materials, radionuclide transport and groundwater chemistry must now be realistically assessed.This work was funded by the UK Department of the Environment and the Commission of the European Communities.

scholarly journals Vitreous Materials for Nuclear Waste Immobilisation and IAEA Support Activities

MRS Advances ◽  
2016 ◽  
Vol 1 (63-64) ◽  
pp. 4201-4206 ◽  
Author(s):  
Rebecca A. Robbins ◽  
Michael I. Ojovan
Keyword(s):  
Radioactive Waste ◽  
Nuclear Waste ◽  
Chemical Elements ◽  
Phosphate Glasses ◽  
Waste Vitrification ◽  
Waste Immobilization ◽  
High Level Nuclear Waste ◽  
Nuclear Waste Immobilization ◽  
High Level ◽  
High Degree

ABSTRACTVitreous materials are the overwhelming world-wide choice for the immobilisation of HLW resulting from nuclear fuel reprocessing due to glass tolerance for the chemical elements found in the waste as well as its inherent stability and durability. Vitrification is a mature technology and has been used for high-level nuclear waste immobilization for more than 50 years. Borosilicate glass is the formulation of choice in most applications although other formulations are also used e.g. phosphate glasses are used to immobilize high level wastes in Russia. The excellent durability of vitrified radioactive waste ensures a high degree of environment protection. Waste vitrification gives high waste volume reduction along with simple and cheap disposal facilities. Although vitrification requires a high initial investment and then operational costs, the overall cost of vitrified radioactive waste is usually lower than alternative options when account is taken of transportation and disposal expenses. Glass has proven to be also a suitable matrix for intermediate and low-level radioactive wastes and is currently used to treat legacy waste in USA, and NPP operational waste in Russia and South Korea. This report is also outlining IAEA activities aiming to support utilisation of vitreous materials for nuclear waste immobilisation.

Transmutation of high-level nuclear waste by means of accelerator driven system

2013 ◽  
Vol 3 (1) ◽  
pp. 60-69 ◽  
Author(s):  
Hamid Aït Abderrahim ◽  
Didier De Bruyn ◽  
Gert Van den Eynde ◽  
Sidney Michiels
Keyword(s):  
Nuclear Waste ◽  
Driven System ◽  
High Level Nuclear Waste ◽  
Accelerator Driven System ◽  
High Level
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