Filtered generated 233 hits.
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2014:05 Technical Note, Assessment of flows to deposition holes – Main Review Phase
SKB’s conceptual model for flow through the fractured rock at Forsmark is based on a division between highly fractured deformation zones (described in terms of deterministic geometry), and the more sparsely fractured rock (described in terms of statistical geometry). The model for the highly fractured deformation zones includes several assumptions that are not strongly supported by data,...
Content type: Publications -
2013:16 Technical Note, Assessment of PWR fuel depletion and of neutron multiplication factors for intact PWR fuel copper canisters – main review phase
SKB (Svensk Kärnbränslehantering AB) in 2011 applied to the Swedish government for approval of a proposed solution for disposal of used fuel from Swedish nuclear power reactors and some relatively minor quantities of other fissile material. This Technical Note contains results of a recent review of the SKB methods used to determine the influence of reactor depletion on keff of intact...
Content type: Publications -
2012:65 Technical Note, Review of the Nuclear Criticality Safety of SKB’s Licensing Application for a Spent Nuclear Fuel Repository in Sweden
The Swedish Nuclear Fuel and Waste Management Company in 2011 applied to the Swedish government for approval of a proposed solution for disposal of used fuel from Swedish nuclear power reactors and some relatively minor quantities of other fissile material. This Technical Note contains results of a recent nuclear criticality safety review of the overall prospects of the application being able...
Content type: Publications -
2013:33 Technical Note, Seismology – Frequencies and mechanisms. -Initial review phase
The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific issues. The...
Content type: Publications -
2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth
The planned Swedish concept for final disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material.
Content type: Publications -
2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?
The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...
Content type: Publications -
2011:08 Workshop on Copper Corrosion and Buffer Erosion Stockholm 15-17 September 2010
In SSM:s preparation for reviewing SKB:s license application for disposal of spent nuclear fuel, a series of technical workshops have been conducted. The main purpose of this type of workshops is to get an overall understanding of the state of knowledge on interdisciplinary issues as well as of questions in the research front by inviting several experts. Previous workshops have addressed the...
Content type: Publications -
2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues
The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...
Content type: Publications -
2011:07 Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing
The Swedish Radiation safety Authority (SSM) is currently developing project plans for the review of the Swedish Nuclear Fuel and Waste Management Co’s (SKB) planned license application for a spent nuclear fuel repository in Forsmark and an encapsulation plant in Oskarshamn. In support of the development of these project plans, SSM has carried out several international workshops during 2010...
Content type: Publications -
2012:35 Technical Note, Review of SKB’s Code Documentation and QA for the SR-Site Safety Assessment
This initial review examined the Swedish Nuclear Fuel and Waste Management Company (SKB) code documentation and quality assurance, which is important to the safety assessment SR-Site because the computer codes used must be both suitable for the analyses performed and capable of producing accurate results for those analyses. SKB has prepared a report that summarizes the code documentation...
Content type: Publications