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Din avgränsning ger 54 träffar.

• 2015:38 Evaluation of fatigue in austenitic stainless steel pipe components

  01 september 2015

  Report number: 2015:38 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Evaluation of fatigue in austenitic stainless steel pipe components 2015:38 Author: Magnus Dahlberg, Dave Hannes, ... Transferability of experimental results obtained for smooth test specimens under constant amplitude loading to realistic components subjected to vari- able amplitude loading is an important issue in the design...

  Innehållstyp: Dokument

• 2015:40 Technical Note, Assessment of flow-related transport parameters used in the SR-Site safety case

  01 oktober 2015

  2015:40 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Assessment of flow-related transport parameters used in the SR-Site safety case 2015:40 Author: Joel E. Geier SSM 2015:40 SSM ... diffusionsdjupet är heterogent och mer begränsat. SKB:s analys av effekter av undersökningsborrhål täcker in de viktigaste fallen som kan öka flödet till deponeringshål, men antalet simuleringar för varje fall...

  Innehållstyp: Dokument

• 2015:49 Technical Note, Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Canister Corrosion Calculations in SR-Site

  01 december 2015

  www.stralsakerhetsmyndigheten.se Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Canister Corrosion Calculations in SR-Site 2015:49 Authors: Steve J. Benbow Richard Metcalfe ... construction and operation of a reposi- tory for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information...

  Innehållstyp: Dokument

• 2015:32 Safe and responsible management of spent nuclear fuel and radioactive waste in Sweden - National Plan

  03 augusti 2015

  www.stralsakerhetsmyndigheten.se Safe and responsible management of spent nuclear fuel and radioactive waste in Sweden Notification of the Swedish National Programme under the Council Directive 2011/70/Euratom ... Ragnarsdotter Thor, Helmuth Zika Safe and responsible management of spent nuclear fuel and radioactive waste in Sweden Notification of the Swedish National Programme under the Council Directive 2011/70/Euratom...

  Innehållstyp: Dokument

• 2015:07 TEM-lamella lift-out from the crack tip region of Alloy 600 for high resolution electron microscopy examination

  10 mars 2015

  the crack tip region of Alloy 600 for high resolution electron microscopy examination 2015:07 Author: Jiaxin Chen SSM 2015:07 SSM 2015:07 SSM perspective Background In light water reactors ... various types of materials are exposed to high temperature and high pressure water environments. The impurities in reactor water may come from corrosion of various reactor materials, degradation of ion exchanger...

  Innehållstyp: Dokument

• 2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load

  01 september 2015

  2000-0456 Available at www.stralsakerhetsmyndigheten.se Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load 2015:37 Author: ... burnups the components of the nuclear fuel are affected by the environment they have been exposed to. Fuel pellets can crack due to thermal effects and tensions build up inside because of fission gases. The...

  Innehållstyp: Dokument

• 2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel

  10 mars 2015

  2000-0456 Available at www.stralsakerhetsmyndigheten.se PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel 2015:09 Author: Peter Dillström SSM 2015:09 SSM 2015:09 SSM ... involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...

  Innehållstyp: Dokument

• 2013:37 Technical Note, Rock Mechanics – Evolution of fracture transmissivity within different scenarios in SR-Site – Main Review Phase

  19 maj 2015

  Available at www.stralsakerhetsmyndigheten.se Rock Mechanics – Evolution of fracture transmissivity within different scenarios in SR-Site – Main Review Phase 2013:37 Author: Ki-Bok Min Jaewon Lee Ove ... med beräkningskoden UDEC och diskreta sprick- nätverksmodeller (DFN-modeller). Resultaten visar bl a att transmissiviteten kan öka upp till två tiopotenser för en spricka med en initiell spricköppning...

  Innehållstyp: Dokument

• 2015:05 Technical Note, Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase

  25 februari 2015

  2015:05 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase Author: Klaus-Jürgen Röhlig SSM 2015:05 ... transmissivitet och sprickstorlek och (ib) den verkliga sprickfördelningen som är okänd men som ska täckas in av de olika realiseringarna av den diskreta spricknätverksmodellen för de olika korrelationsmodellerna...

  Innehållstyp: Dokument

• 2015:30 Technical Note, Rock Mechanics - Assessing the likelihood and extent of fracture growth in the KBS-3 repository at Forsmark

  01 juli 2015

  www.stralsakerhetsmyndigheten.se Rock Mechanics - Assessing the likeli- hood and extent of fracture growth in the KBS-3 repository at Forsmark Main Review Phase 2015:30 Authors: Tobias Backers Tobias ... construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information...

  Innehållstyp: Dokument