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2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
Content type: Publications -
2008:10 User’s manual for Ecolego Toolbox and the Discretization Block
The CLIMB modelling team (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB’s assessment of long-term safety for a geological repository. Modelling in CLIMB covers all aspects of performance assessment (PA) from near-field releases to radiological consequences in the surface...
Content type: Publications -
2008:08 Review of SKB:s Work on Coupled THM Processes Within SR-Can External review contribution in support of SKI:s and SSI:s
The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...
Content type: Publications -
2008:12 Independent Calculations for the SRCan Assessment
External review contribution in support of SKI's and SSI's review of SR-Can The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear...
Content type: Publications -
2008:16 Review of SKB:s Safety Assessment SR-Can: Contributions in Support of SKI:s and SSI:s Review by External Consultants
The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...
Content type: Publications -
2008:18 Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle
Sweden has for many years collected the spent nuclear fuel originating from nuclear power plants. This fuel must at all times be kept under supervision to render a diversion impossible; this is of course due to the possibility to make weapons from the material. One idea is to keep the nuclear material in a repository deep under the ground; this is not only to keep the material safe from theft...
Content type: Publications -
2008:11 Discrete-Feature Modelling of Groundwater Flow and Solute Transport for SR-Can Review
Review External review contribution in support of SKI's and SSI's review of SR-Can. The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for...
Content type: Publications -
SKI Report 2008:01 Reliability Data for piping Components in Nordic Nuclear Poer Plants "R-Book" Project Phase 1
SKI Report 2008:01 - “Reliability Data for Piping Components in Nordic Nuclear Power Plants - R-Book Project Phase I” – is a planning document for a new R&D project to develop a piping component reliability parameter handbook for use in probabilistic safety assessment (PSA) and related activities. Included in this handbook will be pipe leak failure rates and rupture frequencies that are...
Content type: Publications -
2008:06 Synthetic Aperture Focusing Technique in Ultrasonic Inspection of Coarse Grained Materials
Experience from the ultrasonic inspection of nuclear power plants has shown that large focused transducers are relatively effective in suppressing grain (structure) noise. Operation of a large focused transducer can be thought of as an integration (coherent summation) of individual beams reflected from the target and received by individual points at the transducer surface. Synthetic aperture...
Content type: Publications -
2008:30 A model for fission gas release from mixed oxide nuclear fuel
Nuclear fuel containing mixed oxide (MOX) pellets have been used since the 1960´s. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors to be recycled. Producing MOX fuel can be seen as a method to more efficiently use the natural uranium since...
Content type: Publications