Din avgränsning ger 496 träffar.
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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...
Innehållstyp: Publikationer -
2007:42 Regleringen av matarvattenflödet i en PWR - Med exempel från Ringhals 3
Rapporten ger en redovisning av kända och potentiella problem med matarvatten- regleringen i tryckvattenreaktorer, problem som i vissa fall förekommit tidigare internationellt. Vidare ges en detaljerad beskrivning av matarvattenregleringen vid Ringhals 3, som kan sägas vara representativ även för övriga svenska tryckvatten- reaktorer. Analysresultaten visar att R3:s...
Innehållstyp: Publikationer -
2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach
The study used the themes identified in an earlier study: 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 reminders on different aspects of safety management in the nuclear context. reporting, and measurement of...
Innehållstyp: Publikationer -
2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod
The FRAPTRAN-1.3 computer code has been evaluated regarding its applicability, modelling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower transients, reactivity initiated accidents (RIA),...
Innehållstyp: Publikationer -
2007:35 Urananrikning med laser och plasmaseparation - en analys med fokus på exportkontroll
Den nu resulterande rapporten berör kortfattat några generella principer för laseranrikning, både separation av atomärt uran – AVLIS - och separation av uran i molekylär form – MLIS. Vidare berörs mycket översiktligt några andra metoder inklusive plasmaseparation. Dessutom nämns vilken utrustning som kan komma ifråga, indikatorer på laseranrikning,...
Innehållstyp: Publikationer -
SKI Report 2008:01 Reliability Data for piping Components in Nordic Nuclear Poer Plants "R-Book" Project Phase 1
SKI Report 2008:01 - “Reliability Data for Piping Components in Nordic Nuclear Power Plants - R-Book Project Phase I” – is a planning document for a new R&D project to develop a piping component reliability parameter handbook for use in probabilistic safety assessment (PSA) and related activities. Included in this handbook will be pipe leak failure rates and rupture frequencies that are...
Innehållstyp: Publikationer -
2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents
In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...
Innehållstyp: Publikationer -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
Innehållstyp: Publikationer -
2015:50 Assessment of structures subject to concrete pathologies (ASCET)
Many Nuclear Power Plants around the world are at the moment approaching, or in, their Long Term Operation stage of their operational phase. In addition, several NPPs have recently been carrying out uprate and life extension projects and comprehensive maintenance work including the exchange of components important to safety, in order to extend their lifetime. As a result, ageing management...
Innehållstyp: Publikationer -
2015:38 Evaluation of fatigue in austenitic stainless steel pipe components
Background Transferability of experimental results obtained for smooth test specimens under constant amplitude loading to realistic components subjected to variable amplitude loading is an important issue in the design against fatigue. There is a lack of experimental fatigue data for austenitic steel components and the present study is an important contribution to fill this gap. Objective The...
Innehållstyp: Publikationer