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2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA
No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...
Innehållstyp: Publikationer -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
Innehållstyp: Publikationer -
2010:03 Forskningsstrategi 2010-2014
Strålsäkerhetsmyndighetens uppdrag omfattar frågor om skydd av människors hälsa och miljön mot skadlig verkan av joniserande och icke-joniserande strålning, säkerhet i kärnteknisk verksamhet samt nukleär icke-spridning. För att myndigheten ska kunna utföra uppdraget behöver ny kunskap kontinuerligt tillföras verksamheten. Genom...
Innehållstyp: Publikationer -
2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report
The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...
Innehållstyp: Publikationer -
2018:24 Structural equation modelling for analysis of human and organizational factors in nuclear power plant control rooms
SSM perspective Background During the supervisory work of the Swedish Radiation Safety Authority (SSM), a need was identified to develop the methods used when evaluating control room work in the central control rooms of nuclear power plants. Benchmarking is commonly used today, with reference values from earlier Integrated System Validation (ISV), when ISV is available. Often, ISV performs...
Innehållstyp: Publikationer -
2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach
This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...
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 -
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 -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Innehållstyp: Publikationer