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Din avgränsning ger 336 träffar.

• 2007:03 Variability and Uncertainties of Key Hydrochemical Parameters for SKB Sites

  An important part of the site investigations conducted by the Swedish Nuclear Fuel and Waste Management Company (SKB) is the characterisation of groundwater chemical conditions in the deep bedrock environment where a final repository for spent nuclear fuel is planned to be located. This work is currently in its final stages at the two candidate sites, Forsmark and Laxemar, and should be...

  Innehållstyp: Publikationer

• 2007:02 Stakeholder involvement in Swedish nuclear waste management

  This report have attempted to show the development of stakeholder involvement in the siting of a final repository for Sweden’s spent nuclear fuel as resembling something other than a straightforward linear process of improvement and refinement. Stakeholder involvement has developed, over the past 15 years or so, in something more like a patchwork of different shapes and forms. Some of the...

  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

• 2018:25 UO2 fuel oxidation and fission gas release

  Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that has been the main question of several research projects is the fragmentation of fuel pellets during abnormal heat up. In this project the oxidation of UO2 is scrutinized and its effect on pellet fragmentation, fission gas release and damage of fuel rods has been...

  Innehållstyp: Publikationer

• 2016:27 Validation of fatigue fracture mechanics approaches

  Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...

  Innehållstyp: Publikationer

• 2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014

  This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...

  Innehållstyp: Publikationer

• 2016:35 Säkerhetsvärdering mot plastisk kollaps vid skadetålighetsanalyser

  Bakgrund Proceduren som används för brottmekanisk analys av defekter och inspektionsintervall för komponenter i svenska kärntekniska anläggningar utgår från den brittiska R6-metoden men är vidareutvecklad för att ha ett säkerhetsvärderingssystem som är kompatibelt med säkerhetskraven som uttrycks i den amerikanska tryckkärlsstandarden...

  Innehållstyp: Publikationer

• 2016:39 Recommended residual stress profiles for stainless steel pipe welds

  Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations of weld residual stress (WRS) distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on...

  Innehållstyp: Publikationer

• 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

  Ali R. Massih, Lars Olof Jernkvist SSM English...

  Innehållstyp: Publikationer

• 2015:44 Krav på funktion, konstruktion och provning av reaktorinneslutningar

  Bakgrund I Sverige behöver SSM skaffa vidare kunskap inom olika områden inom nukleära byggnadskonstruktioner bl.a. reaktorinneslutningar. Syfte Syftet med projektet "Krav på funktion, konstruktion och provning av reaktorinneslutningar" är att sammanställa information för att belysa viktiga reaktorinneslutningsfrågor vid byggnation. Den sammanställda...

  Innehållstyp: Publikationer