Din avgränsning ger 568 träffar.
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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 -
2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials
SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary stresses for estimating the safety margin against rupture (measured by the J-integral) for the type...
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 -
2018:26 Reaktorinneslutningarnas respons vid höga inre tryck och reducerad förspänning
I föreliggande studie har det genom numerisk modellering undersökts huruvida tillämpning av alternativ B enligt Regulatory Guide 1.90 (R.G. 1.90) är ett tillförlitligt sätt att bedöma reaktorinneslutningens integritet. Vid genomförandet har två olika numeriska modeller använts, en global 3D-modell respektive en ringmodell. Resultaten pekar på...
Innehållstyp: Publikationer -
2018:12 Upparbetning av använt kärnbränsle med icke-vätskebaserade metoder
Bakgrund Sverige har en exportlagstiftning för kontroll av utförsel av speciellt känslig utrustning som kan användas för bl.a. tillverkning av kärnvapen. Syftet är att förhindra att någon stat eller organisation införskaffar sådana vapen. Utrustningen det är frågan om har ofta en legitim användning i civil industri men kan ha...
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 -
2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
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