Filtered generated 275 hits.
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2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Content type: Publications -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Content type: Publications -
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 -
2007:11 Review of Quality Assurance in SKBs Repository Research Experiments
SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. As a preparation for SR-Site SKB has recently produced the SRCan safety assessment, which is currently in review. The assessment of long-term safety is based on a broad range of...
Content type: Publications -
2007:02e Radiation Environment in Sweden, summary
The radiation environment to which the population of Sweden is exposed is dominated by medical investigations and background radiation from the ground and building materials in our houses. That is the conclusion of the first general Swedish summary of environmental monitoring data and dose calculations within the field of radiation. The report shows that people’s behaviour in the form of...
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 -
2005:60 Research and Service Experience with Environmentally-Assisted Cracking in Carbon and Low-Alloy Steels in High-Temperature Water
In this report, the most relevant aspects of research and service experience with environmentally assisted cracking of carbon and low-alloy steels in high-temperature water are reviewed, with special emphasis on the primary pressure-boundary components of boiling water reactors. The main factors controlling the susceptibility to environmentally assisted cracking under light water reactor...
Content type: Publications -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...
Content type: Publications -
2002:04 Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing
The work was finished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was regarded to be of more general interest it is published again as a research report by the Swedish Nuclear Power Inspectorate. To be used in the international cooperation in nuclear safety it was also translated into English by the inspectorate, which is this...
Content type: Publications -
2001:23 Interactions of Severe Accident Researchand Regulatory Positions (ISARRP)
This project, started on April 1, 1999, had the specific objectives of determining whether; (i) the focus of the severe accidents (SA) research is consistent with that of the regulatory authorities, (ii) the results obtained so far by SA research satisfy the regulatory concerns, (iii) the future programs, envisaged will address the potential regulatory needs into next century, and (iv) how...
Content type: Publications