Din avgränsning ger 568 träffar.
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2010:27 Beräkning av merkostnader 2010 -för rivning av de svenska kärnkraftsverken och omhändertagande av restprodukter
Denna rapport beskriver SSM:s beräkningar av merkostnader inför avgiftsförslaget för 2012-2014. Beräkningen görs i enlighet med finansieringslagen och avser samtliga merkostnader fram till dess att restprodukterna från de svenska kärnkraftsverken är slutligt förvarade. Enligt nuvarande beräkningar antas detta ske 2069. Uppskattningar över...
Innehållstyp: Publikationer -
2018:11 Bedömning av spännkraftförluster genom deformationsmätning av reaktorinneslutningen vid uppstart – DEFORM
Bakgrund Den strukturella integriteten av reaktorinneslutningen är beroende av spännarmeringens spännkraft. Spännkraften minskar med tiden genom bl.a. omlagring till själva betongen. I byggnormen finns standardformler som beaktar dessa förluster men lite kunskap finns gällande hur inneslutningens unika geometri och miljö har för inverkan på spännkraftsförlusterna.
Innehållstyp: Publikationer -
2010:41 Rock-block configuration in Uppland and the Ålands-hav basin, the regional surroundings of the SKB site in Forsmark, Sea and land areas, eastern Sweden
This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. The topography in Uppland is more broken in the sea area east and northeast of...
Innehållstyp: Publikationer -
2009:30 A Review of Evidence for Corrosion of Copper by water
The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...
Innehållstyp: Publikationer -
2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...
Innehållstyp: Publikationer -
2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden
A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within the...
Innehållstyp: Publikationer -
2010:23 On Decommissioning Costs of the Ranstad Site
A demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in the context of Swedish as well as European environmental and health...
Innehållstyp: Publikationer -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
Innehållstyp: Publikationer -
2014:28 Numerical simulation of ductile crack growth in residual stress fields
The study has shown on the capability of the cell model in capturing the effects on ductile tearing from limited pre-load levels and a residual stress field. Some of the conclusions are as follows: No distinctive influence on the material fracture toughness is observed from pre-loading (work hardening), both tensile and compressive, at room temperature of 1.5 or 3 % total strain. The cell...
Innehållstyp: Publikationer -
2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects
Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...
Innehållstyp: Publikationer