Sök

Din avgränsning ger 332 träffar.

• 2010:38 The feasibility of Backfilling a Repository of Spent Fuel: An Assessment of Recent Developments by SKB

  In the Review Statement and Evaluation of SKB’s RD & D programme 2007 (SKI Report 2008:48E), the former Swedish Nuclear Power Inspectorate (SKI) commented that considerable work remained to be done for knowledge of both practical management issues on backfilling and analysis of long-term backfill evolution to reach the same level as for the canister and the buffer. SKI considered that the...

  Innehållstyp: Publikationer

• 2010:34 The understanding of the formation of valleys and its implication on site characterization: Moredalen and Pukedalen, south-eastern Sweden

  This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. In south-eastern Sweden, there are a number of over-deepened narrow valleys,...

  Innehållstyp: Publikationer

• 2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads

  Cracked components are usually subjected to loads causing both primary and secondary stresses, e.g. welding components. Engineering assessment approaches, such as the ASME XI code and the R6 procedure, are commonly used to conduct integrity assessment of such components. There has been an ongoing debate how to treat secondary stresses using engineering assessment methods. The nature of these...

  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

• 2011:29 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 17

  This report constitutes Stage 17 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 16 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.

  Innehållstyp: Publikationer

• 2010:39 Beskrivning av Eurokoder för betongkonstruktioner

  Eurokoder, som är gemensamma europeiska standarder för utformning och dimensionering av bärande konstruktioner till byggnader och anläggningar, utarbetas av den Europeiska Standardiseringskommittén (CEN) och ges i Sverige ut av det svenska institutet för standarder (SIS). Sverige, liksom de andra CEN-medlemsländerna, är i färd med att ersätta sina...

  Innehållstyp: Publikationer

• 2011:17 Structural Health Monitoring of Piping in Nuclear Power Plants – A Review of Efficiency of Existing Methods

  SSM needs to acquire knowledge about new applied Non-Destructive Engineering (NDE) techniques and their efficiency. One area that is discussed more frequently is Structural Health Monitoring (SHM). SSM needs to investigate the international experiences of SHM from the nuclear industry. SSM also wants to have more information about the capabilities and the limitations of NDE methods The first...

  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

• 2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)

  Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...

  Innehållstyp: Publikationer

• 2001:36 Kartläggning av strategiskakompetensbehov för kärntekniskverksamhet i nuläget och för framtiden

  SKI skall, på uppdrag av regeringen, före utgången av år 2001 redovisa en uppdaterad strategi för sin framtida inriktning på forskningen och som ett led i detta arbete bedöma det framtida nationella kompetensbehovet och hur detta skall tillgodoses. ES-konsult har i detta sammanhang av SKI fått uppdraget att - genom en till industrin och säkerhetsmyndigheten...

  Innehållstyp: Publikationer