Filtered generated 276 hits.
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2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4
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 -
2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials
SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary stresses for estimating the safety margin against rupture (measured by the J-integral) for the type...
Content type: Publications -
2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report
The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...
Content type: Publications -
2014:30 Modelling Approaches to C-14 in Soil-Plant Systems and in Aquatic Environments
Substantial expertise on carbon biogeochemistry already exists in the fields of plant physiology and aquatic ecology and therefore is it beneficial to draw on this to identify the important issues. A paper describing the BIOPROTA C-14 model inter-comparisons, and plans for the forward programme was published in Radiocarbon Journal. Further studies on C-14 (including modelling, model...
Content type: Publications -
1999:13 Determination of the Neutron and Photon Dose Equivalent at Work Places in Nuclear Facilities of Sweden
Various mixed neutron-photon fields at workplaccs in the containment of pressurised water reactors and in the vicinity of transport containers with spent fuel elements were investigated with spectrometers and dosimeters.The spectral neutron fluences evaluated from measurements with multisphere systems were recommended to be used for the calculation of dosimetric reference values for...
Content type: Publications -
2013:07 Corrosion of copper in distilled water without molecular oxygen and the detection of produced hydrogen
In this report, results are presented for copper which has been exposed to pure anoxic water in the temperature interval of 21 °C to 55 °C up to a total of 19 000 hours. Characterisations of copper surfaces after exposure have been performed ex-situ, meaning after termination of the experiment and exposing the specimen to normal atmospheric environment. Ideally characterisation of surfaces...
Content type: Publications -
2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden
A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within 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 -
2010:23 On Decommissioning Costs of the Ranstad Site
A demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in the context of Swedish as well as European environmental and health...
Content type: Publications -
2009:31 A Review of the Decommissioning Costs of the Ranstad Site
The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary “bench-marking” studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been...
Content type: Publications