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Din avgränsning ger 76 träffar.

• 2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report

  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 ... the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code. Paul Scott, Robert Kurth, Andrew Cox, Rick Olson and Dave...

  Innehållstyp: Publikationer

• 2011:05 Overview and Evaluation of the NESC Projects for Fracture Assessments of Nuclear Components

  Evaluation of Structural Components (NESC) was started in 1993 and since then six different projects have been carried out. A seventh NESC-project is still in progress. The overall objective of these projects ... reliability of the entire process of structural integrity assessment within an international framework. The network is coordinated by the European Commission’s Joint Research Centre (JRC) in Petten, Netherlands...

  Innehållstyp: Publikationer

• 2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth

  disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective ... objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material. A very dilute groundwater chemical condition...

  Innehållstyp: Publikationer

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

  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 ... development of these project plans, SSM has carried out several international workshops during 2010 on detailed technical review issues including radionuclide transport, earthquakes, properties of the spent...

  Innehållstyp: Publikationer

• 2010:36 Guidance for the Definition and Application of Probabilistic Safety Criteria

  goals are defined in different ways in different countries and also used differently. Many countries are presently developing them in connection to the transfer to risk-informed regulation of both operating ... for the interpretation of results from a probabilistic safety assessment (PSA), and they tend to enhance the quality and realism of a risk assessment. On the other hand, strict use of probabilistic criteria...

  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 ... results. Simulated sampling of fractures in boreholes does not indicate any reason to exclude the proposed spatial and structural relationships among fractures. The number of deposition holes that need...

  Innehållstyp: Publikationer

• 2010:35 Probabilistic Safety Goals for Nuclear Power Plants; Phases 2-4 / Final Report

  goals are defined in different ways in different countries and also used differently. Many countries are presently developing them in connection to the transfer to risk-informed regulation of both operating ... for the interpretation of results from a probabilistic safety assessment (PSA), and they tend to enhance the quality and realism of a risk assessment. On the other hand, strict use of probabilistic criteria...

  Innehållstyp: Publikationer

• 2011:10e Review and evaluation of the Swedish Nuclear Fuel and Waste Management Company’s RD&D Programme 2010. Statement to the Government and summary of the review report

  In accordance with Section 25 of the Ordinance (1984:14) on Nuclear Activities (Nuclear Activities Ordinance), the Swedish Radiation Safety Authority (SSM) shall review and assess the research, development ... demonstration programme (RD&D programme) that the reactor licensees are obligated to establish in accordance with the Act (1984:3) on Nuclear Activities (Nuclear Activities Act). The Swedish Nuclear Fuel and...

  Innehållstyp: Publikationer

• 2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads

  to conduct integrity assessment of such components. There has been an ongoing debate how to treat secondary stresses using engineering assessment methods. The nature of these assessment approaches is to ... assessments. These two approaches treat the issue of secondary stresses differently. The ASME XI code does not consider weld-induced residual stresses in some materials, for instance stainless steel welds...

  Innehållstyp: Publikationer

• 2011:14 Rapport från SSM:s vetenskapliga råd om ultraviolett strålning 2010

  15 april 2011

  3531 ... . 14 Förstadier till invasiv skivepitelcancer i huden: Aktiniska keratoser och skivepitelcancer in situ, Mb Bowen ............................................. 15 Definition och patogenes ....... ... Figur 1. Ålderstandardiserad incidens för invasiva hudmelanom i Sverige. (från ”Cancer Incidence in Sweden 2009”. Socialstyrelsen 2010) Det föreligger stora geografiska skillnader inom Sverige...

  Innehållstyp: Dokument