Filtered generated 375 hits.
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2007:08 DECOVALEX-THMC - Task B
This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...
Content type: Publications -
2008:48E Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co´s (SKB) RD&D Programme 2007
The review of the RD&D Programmes (Research, Development, Demonstration) prepared by the Swedish Nuclear Fuel and Waste Management Co (SKB) is a recurrent task that the Swedish Nuclear Power Inspectorate (SKI) must carry out as a regulatory authority with the support of reviewing bodies of which the most important is the Swedish Radiation Protection Authority (SSI). The review statement for...
Content type: Publications -
2007:30 Modelling the Interaction of Low pH Cements and Bentonite
Concrete and cement are used in constructions as well as in conditioning of waste inrepositories for radioactive waste. It is well known that in the hyperalkaline conditions (pH > 12) of standard cement pore fluids, there is potential for deleterious effects upon the host rock and other EBS materials, notably bentonite, in geological repositories. Low pH cements are beginning to be considered...
Content type: Publications -
2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment
The objective of this study is to understand how data for groundwater compositions were used in producing the Site Descriptive Model for Forsmark and as input data for the safety assessment, SRSite. Improving this understanding sheds further light on the significance of data uncertainties, data processing and interpretation on the degree of uniqueness in the descriptive model, parameterisation...
Content type: Publications -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...
Content type: Publications -
2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach
This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...
Content type: Publications -
2018:17 Assessment of structures subject to concrete pathologies (ASCET), phase 2
Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE4 Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to aging of concrete structures.
Content type: Publications -
2014:27 Regulation applying to welding of pressure equipment – a comparative study
The PED was in force in November 1999 and has been mandatory in European Union Member States since May 2002. Most of the standards referred to in the PED are relatively new although some of the standards were adopted in the early 1990s. On the other hand, the ASME B&PV Code has been used for a long time now and is the result of several decades of industrial experiences. The authors present...
Content type: Publications -
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 -
2014:09 Further Development of the Core Simulator CORE SIM: Extension to coupled capabilities for BWRs
The developed tool is fully MatLab based and requires a set of input data from a commercial static core simulator. The driving perturbation can be specified both as a perturbation in thermo-hydraulic parameters or directly as a perturbation in macroscopic cross-sections. As output, the 3-dimensional spatial distribution of the noise in coolant density, pressure, enthalpy, inlet velocity, fuel...
Content type: Publications