Filtered generated 754 hits.
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02:03 Natural Elemental Concentrations and Fluxes: Their Use as Indicators of Repository Safety
Bill Miller, Andy Lind, Dave Savage, Philip Maul, Peter Robinson SKI English...
Content type: Publications -
98:41 Statistical Patterns of Geochemistry in Crystalline Rock and Effect of Sorption Kinetics on Radionuclide Migration
S. Xu, A. Wörman SKI English...
Content type: Publications -
01:38 Galvanic and Stress Corrosion of Copper Canisters in Repository Environment. A Short Review
Hans-Peter Hermansson, Martin König SKI English...
Content type: Publications -
2004:56 Whiskers and Localized Corrosion on Copper in Repository Environment
Hans-Peter Hermansson, Peter Gillén SKI English...
Content type: Publications -
2003:23 Creep of the Copper Canister A Critical Review of the Literature
William H. Bowyer SKI English...
Content type: Publications -
01:04 SKI and SSI's Joint Review of SKBs Safety Assessment
SKI,SSI English...
Content type: Publications -
2013:08 Licensing of safety critical software for nuclear reactors
It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors.
Content type: Publications -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
Content type: Publications -
2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7
The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...
Content type: Publications -
2013:04 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 18
The program executed in Stage 18 consists of the following three parts: Application of CoreSim with a two-dimensional model of vibrating fuel assemblies, for the calculation of ex-core detector noise throughout a fuel cycle; An investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of...
Content type: Publications