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  • 2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components

    procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of intense study ... study in USA, Japan and elsewhere. Several reports indicate a potentially large influence of the environment, leading to the proposal of entirely new calculation procedures. The background for the new design...

    Innehållstyp: Publikationer
  • 2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen

    difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental ... problems with leakage resulted in that the research program originally planned for in this project had to be reduced considerable. Nevertheless, experimental work conducted in this project has in principle...

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

    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 ... parameters that account for the Nordic and worldwide service experience with safety-related and non-safety-related piping systems in a consistent and realistic manner. The report aims to demonstrate the complete...

    Innehållstyp: Publikationer
  • 2011:11 Handling Interfaces and Time-varying Properties in Radionuclide Transport Models

    the same release as larger fractures with the same pore velocity, so a channel enhancement factor of √10 should be considered. A spalling zone that increases the area of contact between flowing water and ... the effects of glacial episodes on radionuclide transport with time-varying properties. The simulation results show that for both single and multiple glacial episodes the time-dependency of model parameters...

    Innehållstyp: Publikationer
  • 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
  • 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
  • 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