Din avgränsning ger 332 träffar.
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2001:23 Interactions of Severe Accident Researchand Regulatory Positions (ISARRP)
This project, started on April 1, 1999, had the specific objectives of determining whether; (i) the focus of the severe accidents (SA) research is consistent with that of the regulatory authorities, (ii) the results obtained so far by SA research satisfy the regulatory concerns, (iii) the future programs, envisaged will address the potential regulatory needs into next century, and (iv) how...
Innehållstyp: Publikationer -
1994:14 Evaluation of acceptance criteriafor data on environmentally assistedcracking in light water reactors
The assessment of possible sub-critical crack growth through environmentally assisted cracking (EAC) is a commonly encountered problem in safety evaluations of light water reactor components. The numerous factors influencing EAC fall into three main groups (material, medium and loading), but their interactions are highly complex. Field assessments usually rely on the evaluation of...
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 -
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 -
2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures
The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...
Innehållstyp: Publikationer -
2007:09 DECOVALEX-THMC - Task C
This report describes the results of Task C1 of the international DECOVALEX– THMC project devoted to Excavation Damage Zone (EDZ) in argillaceous rock at the Tournemire site in France. Task C of the project is aimed to understand the physical phenomena induced by excavation in the argillaceous rock. The task is to develop adequate numerical models for interpretation of observed damaged zones...
Innehållstyp: Publikationer -
2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C
The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...
Innehållstyp: Publikationer -
2008:12 Independent Calculations for the SRCan Assessment
External review contribution in support of SKI's and SSI's review of SR-Can The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear...
Innehållstyp: Publikationer -
2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden
The aim of this applied study has been to demonstrate how a cost calculation is done in a systematic way. The framework of the project has been limited to older nuclear installations in Sweden. Furthermore, it may be envisaged that the process of making regular estimates of all the parameters is crucial in preparatory phases of decommissioning and dismantling processes. A secondary aim of the...
Innehållstyp: Publikationer -
2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark
SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...
Innehållstyp: Publikationer