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Din avgränsning ger 42 träffar.

• 2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?

  The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...

  Innehållstyp: Publikationer

• 2011:08 Workshop on Copper Corrosion and Buffer Erosion Stockholm 15-17 September 2010

  In SSM:s preparation for reviewing SKB:s license application for disposal of spent nuclear fuel, a series of technical workshops have been conducted. The main purpose of this type of workshops is to get an overall understanding of the state of knowledge on interdisciplinary issues as well as of questions in the research front by inviting several experts. Previous workshops have addressed the...

  Innehållstyp: Publikationer

• 2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues

  The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...

  Innehållstyp: Publikationer

• 2011:03 On Decommissioning Cost for Nuclear Power Plants

  This research report summarizes what has changed over the latest 15 years concerning actual and estimated costs for the D&D of nuclear power plants that have been shut down permanently. It also reports on the availability of detailed information for actual nuclear power plant D&D cost breakdowns. The results will be one supporting document in the review of the estimates submitted for...

  Innehållstyp: Publikationer

• 2011:07 Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

  The Swedish Radiation safety Authority (SSM) is currently developing project plans for the review of the Swedish Nuclear Fuel and Waste Management Co’s (SKB) planned license application for a spent nuclear fuel repository in Forsmark and an encapsulation plant in Oskarshamn. In support of the development of these project plans, SSM has carried out several international workshops during 2010...

  Innehållstyp: Publikationer

• 2011:20 A Guidebook for Evaluating Organizations in the Nuclear Industry – an example of safety culture evaluation

  Organizations in the nuclear industry need to maintain an overview on their vulnerabilities and strengths with respect to safety. Systematic periodical self- assessments are necessary to achieve this overview. This guidebook provides suggestions and examples to assist power companies but also external evaluators and regulators in carrying out organizational evaluations. Organizational...

  Innehållstyp: Publikationer

• 2011:06 Reliability Data Handbook for Piping Components in Nordic Nuclear Power Plants – R Book, Phase 2

  The Nordic PSA Group (NPSAG) has undertaken to develop a piping reliability parameter handbook for use in risk-informed applications that involve the consideration of structural integrity of piping systems. The scope of the handbook is to establish high quality reliability parameters that account for the Nordic and worldwide service experience with safety-related and non-safety-related piping...

  Innehållstyp: Publikationer

• 2011:16 Modelling of ultrasonic testing of cracks in cladding

  During the last two decades, SSM has supported research to develop a model for the non-destructive test situation based on ultrasonic technique. Such a model is important in many ways, for example to supplement and plan experimental studies and to perform parametric studies in qualification situation. Modeling can be a useful tool when the inspection system shall be technically justified.

  Innehållstyp: Publikationer

• 2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark

  Flow modelling using alternative assumptions regarding conceptual and parametric uncertainty in the spatial and structural relationships among fractures indicates elevated flow rates and groundwater velocities to deposition holes compared to SKB’s flow modelling results. Simulated sampling of fractures in boreholes does not indicate any reason to exclude the proposed spatial and structural...

  Innehållstyp: Publikationer

• 2011:02 The Back-End of the Nuclear Fuel Cycle in Sweden, Considerations for safeguards and data handling

  The report is a compilation report consisting of three papers. A safeguards approach for the planned encapsulation facility and the operating final repository is presented in paper 1. Special considerations concerning safeguards for the final disposal process have been discussed and incorporated into the approach. Paper 2 defines the spent fuel data that must be secured, for safeguards...

  Innehållstyp: Publikationer