Din avgränsning ger 571 träffar.
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1994:28 ”SKIFTNYCKELN”
Denna uppsats beskriver utvecklingen av en metod för bedömning och analys av kommunikation och samspel i kontrollrum på ett kärnkraftverk. Utifrån en övergripande litteraturgenomgång samt intervjuer med berörd personal vid KSU (Kärnkraft-Säkerhet Utbildning) och Ringhals kärnkraftverk konstruerades ett verktyg anpassat för utvärdering...
Innehållstyp: Publikationer -
1994:15 Aging Degradation of Concrete Structures in Nuclear Power Plants
This report on the aging-related degradation of concrete structures in nuclear power plants was prepared by Battelle Seattle Research Center for the Swedish Nuclear Power Inspectorate (SKI). The purpose of this report is to provide an understanding of how concrete structures in nuclear power plants degrade over time. This report is based on the studies of concrete aging commissioned by the...
Innehållstyp: Publikationer -
2012:02 Evaluation of activity build-up experiments
This project aims to understand how the water chemistry affects the activity build-up on surfaces in different systems in Swedish nuclear power plants, which in turn provides information on conditions required to reduce the radiation exposure to power plant staff. The study was done to obtain knowledge about water chemistry conditions preferred to minimize the activity build-up. A number of...
Innehållstyp: Publikationer -
1996:70 Risks from Nuclear Waste
The first part of this review discusses the importance of risk. Man seems to have a longing for risks, like a part of the human nature. If risks are missing, they have to be invented, as needed parts in the emotional attraction of sports, amusement parks, traveling, etc.; this is the emotional part of risk. There is also a rational part of risk, in selecting such objects in ordinary life big...
Innehållstyp: Publikationer -
1995:70 Crack Characterisation for In-service
During in-service inspection by non destructive testing the reliability is highly dependent on how the equipment is adjusted to the specific object and to the anticipated crack features. The crack feature and morphology vary widely between different cracking mechanisms and between material types, in which the cracks appear. The major objective of this study was to characterise a number of...
Innehållstyp: Publikationer -
96:51 The Flooding Incident at the Ågesta Pressurized Heavy Water Nuclear Power Plant
This report is a Master's thesis in Nuclear Reactor Engineering to be submitted to the SKi (Swedish Nuclear Power Inspectorate). The work has been performed at the Division of Nuclear Power Safety, KTH,Stockholm. It is an independent investigation of the consequences of the flooding incident at the Agesta HPWR, in Stockholm, Sweden, which occurred on the 1st of May 1969. The issue was raised...
Innehållstyp: Publikationer -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
Innehållstyp: Publikationer -
2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
Innehållstyp: Publikationer -
2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can
In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The report represented the culmination of work conducted by SKB over several years, focusing on the goal of making the licence application in late 2009. Results from the SR-Can project have been documented in several...
Innehållstyp: Publikationer -
2008:08 SSI:s independent consequence calculations in support of the regulatory review of the SR-Can safety assessment
With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB’s capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to...
Innehållstyp: Publikationer