Filtered generated 146 hits.
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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 -
2012:42 Technical Note, Initial review of physical properties and processes of the buffer and backfill – Installation and initial state
The technical note briefly summarises the proposed designs and functions of the buffer and backfill, and examines SKB’s progress in manufacturing, installing and testing its proposed solutions. In brief, the review suggests that there are some procedural and practical engineering aspects (e.g., quality assurance procedures, backfilling rates) and several physical processes to do with the...
Content type: Publications -
2012:29 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes
De dokument i SR-Site som är relevanta till detta granskningsområde bedöms vara generellt i tillräckligt hög kvalitet för att utgöra underlagsmaterial för vidare granskning i huvudgranskningsfasen av SSM:s GLS- (granskning av långsiktig säkerhet) projekt. Behov av kompletterande information eller förtydliganden har dock identifierats inom...
Content type: Publications -
2012:13 Technical Note, A review of the creep ductility of copper for nuclear waste canister application
SKB has presented insufficient evidence to justify their position that the OFP copper has an adequate creep ductility during long term storage. Their large body of experiments only serves to prove that the creep ductility is sufficient for much shorter time spans than the intended storage times. There is a clear need for a credible theory of creep brittleness of OFP copper which will permit...
Content type: Publications -
1997:05 SKI SITE-94
The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...
Content type: Publications -
2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models
In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...
Content type: Publications -
2016:09 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – radionuclide transport, dose assessment, and safety analysis methodology
Initial review phase SSM English Initial review phase...
Content type: Publications -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...
Content type: Publications -
2024:13 Technical Note, Review of recent research activities conducted by SKB relating to hydro geological aspects of the disposal of radioactive waste
SSM perspective Background The Swedish Radiation Safety Authority (SSM) examines the Swedish Nuclear Fuel Company’s (SKB) applications in a step-wise review and approval process according to the government’s licence conditions under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a geological disposal facilities. As part of the review, SSM commissions...
Content type: Publications -
2014:35 Technical Note, Modelling comparison of alternative biosphere models with LDF models and evaluation of selected parameter values used in the biosphere dose assessment - Main review phase
This report has been prepared as part of the SSM’s Main Review Phase of SKB’s SR-Site performance assessment of the long-term safety of the KBS-3 geological disposal facility (GDF) proposed for construction at Forsmark. The review addresses the methodology employed in the dose assessment calculations of SR-Site; specifically issues of transport, accumulation and transfers of radionuclides in...
Content type: Publications