Filtered generated 289 hits.
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2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel
Following an OCDE round robin proposal, 16 participants from 9 countries (USA, Japan, Korea (6 participants), Sweden, Germany, Czech Republic, Spain, EC and France (3 participants)) have been involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...
Content type: Publications -
2016:26 Ensemble for deterministic sampling with positive weights
The aim of this project is to find a reliable method for determining an ensemble for Deterministic Sampling with only positive weights. This report is intended to work as a presentation of the project, as well as to work as a beginner’s guide to DS. In the report several methods for generating DS ensembles are presented, which can encode up to four moments and represent any kind of...
Content type: Publications -
2019:23 Participation in the European Committee for Standardization's workshop regarding civil structures
SSM perspective Background During the period 2014-2018, a CEN1 workshop (Phase 2 Prospective Group 3 civil works) have been carried out. The aim of the workshop is to provide a base founded on the French standard in order to be able to establish a possible future European standard for the design of civil structures at nuclear power plants. The workshop has identied which additional...
Content type: Publications -
2007:39 Influence of Crack Morphology on Leak Before Break Margins
The SKI regulation SKIFS 2004:2 allows for the use of Leak Before Break (LBB) as one way to provide assurance that adequate protection exists against the local dynamic consequences of a pipe break. The way to demonstrate that LBB prevails relies on a deterministic procedure for which a leakage crack is postulated in certain sections of the pipe based on the leak detection capability of the...
Content type: Publications -
2007:24 Safety Management in Non-Nuclear Contexts Examples from Swedish Railway Regulatory and Company Perspectives
The authors describe important features of safety management and the results are modelled according to the systems perspective developed. These are definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reporting, and...
Content type: Publications -
2007:14 Review of experimental data for modelling LWR fuel cladding behaviour under loss of coolant accident conditions
This project has contributed to the research goal of giving a basis for SKIs supervision by means of evaluating experimental data and modelling the nuclear fuel cladding during a design base accident. The project has also contributed to the research goal to develop the competence about licensing of fuel at high burnup, which is an important safety issue. The results are useful as such, but...
Content type: Publications -
Research activities
Research activities in the field of nuclear safety and radiation protection encompass a broad spectrum of aspects in terms of nuclear safety, radiation protection and nuclear non-proliferation. Nuclear non-proliferation activities imply preventing nuclear material and equipment for civilian purposes from being used to manufacture nuclear weapons.
Content type: Regular Pages -
IAEA IRRS-mission report to Sweden published
The International Atomic Energy Agency, IAEA, has reviewed Sweden’s framework for nuclear safety and radiation protection, the so-called IRRS review (Integrated Regulatory Review Service). The review is carried out every ten years by a group of international experts led by a team from the IAEA. Sweden’s second full-scope IRRS-review was carried out 14 – 25 November 2022. The report has now...
Content type: News -
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...
Content type: Publications -
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...
Content type: Publications