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Din avgränsning ger 1334 träffar.

• 1997:40 Aging of Electrical Components in Nuclear Power Plants

  The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. The study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of...

  Innehållstyp: Publikationer

• 96:77 Common Cause Failure Analysis of Hydraulic Scram and Control Rod Systems in the Swedish and Finnish BWR Plants

  Tuomas Mankamo SKI English...

  Innehållstyp: Publikationer

• 96:63 Riskanalys i MTO-perspektiv summering av metoder för industriell tillämpning

  L. Harms-Ringdahl SKI Svenska...

  Innehållstyp: Publikationer

• 99:34 APRI 3 - Accident Phenomena of Risk Importance

  Final report...

  Innehållstyp: Publikationer

• 95:67 Analysis Tools for Reliability Databases

  J. Dorrepaal SKI English...

  Innehållstyp: Publikationer

• 99:29 Erosionkorrosion

  Behnaz Aghili SKI Svenska...

  Innehållstyp: Publikationer

• 2020:07 Fibre Clogging in Nuclear Power Plants

  SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to out foreign material suspended in the cooling water so this material does not reach the reactor. After the 1992 event at Barsebäck nuclear power plant when the strainers of the emergency cooling system was clogged due to fibers in the cooling water, all...

  Innehållstyp: Publikationer

• 2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants

  SSM perspective Background As the nuclear power plants are ageing, it is important to verify that every component installed can function safely in the intended environment. Cables are among the most common components in a nuclear power plant and are required to function during normal operation as well as in the event of an accident. There is a need within the nuclear industry for...

  Innehållstyp: Publikationer

• 2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling

  SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs...

  Innehållstyp: Publikationer

• 2021:06 Quality Assurance Review of the Swedish Nuclear Fuel and Waste Management Company’s LOT Experiment (Phase S2 and A3) at the Äspö Facility in Sweden

  SSM perspective Background This report presents a quality assurance (QA) review of the work done by SKB to retrieve the S2 and A3 parcels from the Long term test of buffer material (the LOT experiment) at the Äspö Hard Rock Laboratory. Each LOT parcel comprises a heated copper tube surrounded by bentonite, with a number of copper coupons and various other test and monitoring instruments...

  Innehållstyp: Publikationer