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Din avgränsning ger 565 träffar.

• 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

• 2018:24 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

• 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

• 2012:07 Implementation of the Master Curve method in ProSACC

  Cleavage fracture toughness data display normally large amount of statistical scatter in the transition region. The cleavage toughness data in this region is specimen size-dependent, and should be treated statistically rather than deterministically. The Master Curve (MC) methodology is a procedure for mechanical testing and statistical analysis of fracture toughness of ferritic steels in the...

  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

• 2008:49 En studie av olycksutredningsmetoders utveckling: En sammanställning över “State-of-the-Art”

  Projektets syfte var att kartlägga de huvudsakliga olycksutredningsmetoder som utvecklats sedan början av 1990-talet. Motivationen är den ökande frekvensen av olyckor som sätter sig upp mot förklaringar i enkla termer, så som orsak-verkanskedjor eller mänskliga fel. Medan komplexiteten hos sociotekniska system är stadigt ökande i alla industriella...

  Innehållstyp: Publikationer

• 2009:15 Improvement and Validation of Weld Residual Stress Modelling Procedure

  Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...

  Innehållstyp: Publikationer

• 2008:13 Rekommendationer för analys av spänningsrespons i rörsystem utsatta för termohydrauliska transienter

  Snabba termohydrauliska transienta förlopp, t.ex. vattenslag på grund av momentant rörbrott eller ventilstängning, leder till strukturbelastningar som är högfrekventa i sin natur. För dessa laster finns inga enkla analyskriterier att tillgå för att påvisa fullständigheten i den beräknade spänningsresponsen i röret. De mest väsentliga...

  Innehållstyp: Publikationer

• 2007:31e Safety and Radiation Protection at Swedish Nuclear Power Plants 2006

  Safety related problems in the electric systems of the Forsmark 1 reactor were the dominant event in Swedish nuclear power plants in 2006. The incident has had a significant impact on our attitude towards the reliability of how safety systems function both in Sweden and abroad. In connection with SKI’s review of the incident it was found that the company’s management system was not...

  Innehållstyp: Publikationer

• 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