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Din avgränsning ger 87 träffar.

• 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

• 2011:06 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

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

  The Network for 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 has been to study the reliability of the entire process of structural integrity assessment within an international framework. The network is coordinated by the European...

  Innehållstyp: Publikationer

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

  During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design 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...

  Innehållstyp: Publikationer

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

  Safety 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 nuclear power plants (NPP) and new designs. However, it is far from self-evident how probabilistic safety criteria should be defined and used. On one hand, experience indicates that...

  Innehållstyp: Publikationer

• 2010:47 Utveckling av programpaket för analys av termisk utmattning

  I ett tidigare NESC-projekt (Network for Evaluating Structural Components – Thermal Fatigue) togs fram en Europeisk procedur för hantering av termisk utmattning. Den tidigare myndigheten Statens kärnkraftinspektion (SKI) var en av projektets finansiärer. Proceduren innehåller bl.a. utvärdering av en modell för analys av högcykelutmattning vid turbulent termisk...

  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

• Ofrivillig genomlysning vid ortopedoperation

  Under en operation på ortopedkliniken kom av misstag en exponeringsutlösande pedal till genomlysningsutrustningen i kläm. Den sövda patienten genomlystes i 4 minuter och 55 sekunder innan utrustningens larm utlöstes och personalen i operationssalen upptäckte vad som skett och stängde av utrustningen. Personalen som befann sig i operationssalen bar vid tillfället...

  Innehållstyp: Artiklar

• Felaktigt kalibreringscertifikat levererat med Ir-192 källa

  Vid rutinmässigt Ir-192 källbyte vid en brachyterapienhet upptäckte ansvarig sjukhusfysiker en signifikant skillnad på 7,5 procent mellan tillverkarens certifierade dosrat och kontrollmätt dosrat, vilket överskrider den osäkerhet tillverkaren uppger och de toleransgränser sjukhuset har.

  Innehållstyp: Artiklar

• Patienter får fel radiofarmaka

  Under 2011 har Strålsäkerhetsmyndigheten mottagit anmälningar från fyra sjukhus om missöden där patienter har administrerats fel radiofarmaka i samband med diagnostiska undersökningar. I samtliga fall har personalen missat någon av de kontroller som finns från beredning av radiofarmaka till administration. De inblandade hade olika lång erfarenhet...

  Innehållstyp: Artiklar