Filtered generated 373 hits.
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2010:24 On Cost Estimate for Decommissioning of one Isotope Central
The present generation has the responsibility to ensure and guarantee that sufficient financial resources are accrued into the Swedish Nuclear Waste Fund to cover all future costs. Thus, the next generation, as well as any succeeding generations, will have the financial resources required in order to undertake the necessary measures, in an appropriate manner, for the decommissioning and...
Content type: Publications -
2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method
The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...
Content type: Publications -
2008:10 International Expert Review of SR-Can: Engineered Barrier Issues
The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...
Content type: Publications -
2007:29 Intercomparison of Cement Solid-Solution Models
Many concepts for the geological storage of radioactive waste incorporate cement based materials, which act to provide a chemical barrier, impede groundwater flow or provide structural integrity of the underground structures. Thus, it is important to understand the long-term behaviour of these materials when modelling scenarios for the potential release and migration of radionuclides. In the...
Content type: Publications -
2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2
Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly described in the code. The...
Content type: Publications -
2017:34 Human capability to cope with unexpected events är publicerad
Background In the light of the Fukushima accident, it stood clear that the challenge of the unexpected is of great importance to both regulators and licensees. For SSM, as for many other national regulators, there was a selfevident need to learn more about the capabilities and actions of people when the unexpected arises and conditions are potentially extreme. A task group was set up within...
Content type: Publications -
2019:16 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU
– consequence analysis and hydrogeological aspects Main review phase...
Content type: Publications -
2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study
SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...
Content type: Publications -
2020:15e Protective Actions in Nuclear or Radiological Emergencies - Planning Basis for Events in Emergency Preparedness Category IV
In this report, the Swedish Radiation Safety Authority (SSM) presents planning basis for protective actions in the event of nuclear or radiological emergencies in connection with activities and acts in emergency preparedness category IV. Activities and acts encompass events in activities with ionizing radiation that are not conducted in a specifically defined location as well as antagonistic...
Content type: Publications -
2021:04 Calibration of models for cladding tube high-temperature creep and rupture in the FRAPTRAN-QT-1.5 program
SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs...
Content type: Publications