Filtered generated 401 hits.
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2011:12 Analysis of Barrier Performance: Modelling of Copper corrosion scenarios with and without buffer erosion
The purpose of this project was to develop a numerical modelling capacity to address the corrosion of the copper canister under gradually changing transport conditions caused by buffer erosion and removal of buffer mass. Due to the complexity of this task, such a model cannot be realistic in all respects, but the present effort should address the feasibility of solving numerical and...
Content type: Publications -
2010:38 The feasibility of Backfilling a Repository of Spent Fuel: An Assessment of Recent Developments by SKB
In the Review Statement and Evaluation of SKB’s RD & D programme 2007 (SKI Report 2008:48E), the former Swedish Nuclear Power Inspectorate (SKI) commented that considerable work remained to be done for knowledge of both practical management issues on backfilling and analysis of long-term backfill evolution to reach the same level as for the canister and the buffer. SKI considered that the...
Content type: Publications -
2011:11 Handling Interfaces and Time-varying Properties in Radionuclide Transport Models
Quintessa’s QPAC code has been used to investigate the Qeq approach. The conclusions from this simulation study are the following. The basic approach to calculating Qeq values is sound, however, narrow channels could lead to the same release as larger fractures with the same pore velocity, so a channel enhancement factor of √10 should be considered. A spalling zone that increases the area of...
Content type: Publications -
2012:08 Deterministic Assessment of Future Costs for Dismantling (FA)
In this study a model for advanced deterministic cost calculation has been used to find a parametric value on the cost for dismantling of the FA-facility. The study gives good description of good practise to collect, test and utilise input data in a systematic way in order to make prudent cost estimates for any particular nuclear installation The Swedish Law stipulates that future expenses...
Content type: Publications -
2012:15 Technical Note, A review of the mechanical integrity of the canister
An introductory review of SR-Site has been conducted with respect to the mechanical integrity of the canister. The review is focused on the copper canister and the nodular cast iron insert. Review results show that a number of loads and loading scenarios for the copper canister has not been analysed by SKB. The importance of sufficient creep ductility of the copper material and sufficient...
Content type: Publications -
Pronouncement on repository applications made to the Swedish Government
On 23 January 2018, the Swedish Radiation Safety Authority, SSM, in its capacity as a preparatory authority, submitted its pronouncement to the Government regarding SKB's licence applications for final disposal of spent nuclear fuel. SSM recommends approval of SKB's applications under the Act on Nuclear Activities for licences to construct a repository for spent nuclear fuel, located at...
Content type: Regular Pages -
2015:18 Uranium Aerosol Characteristics at a Nuclear Fuel Manufacturing Site - Particle Size, Morphology and Chemical Composition
Vid alla kärntekniska verksamheter krävs att strålningsmiljön kontrolleras dels genom mätningar av ytors- och luftens kontamination i anläggningen och dels med persondosimetriverksamhet inkluderat helkroppsmätning. De olika metoder som används för att beräkna intecknad effektiv stråldos från kontinuerligt intag via inandning är förknippade...
Content type: Publications -
2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents
In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...
Content type: Publications -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
Content type: Publications -
2015:50 Assessment of structures subject to concrete pathologies (ASCET)
Many Nuclear Power Plants around the world are at the moment approaching, or in, their Long Term Operation stage of their operational phase. In addition, several NPPs have recently been carrying out uprate and life extension projects and comprehensive maintenance work including the exchange of components important to safety, in order to extend their lifetime. As a result, ageing management...
Content type: Publications