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Din avgränsning ger 108 träffar.

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

  The current review assignment consists of a literature review and independent modeling for assessing the importance of fracture transmissivity change especially driven by shear loading due to SKB’s thermal ... repository at Forsmark. In the first part of the report, SKB’s laboratory experiments on shear fracture dilation and extensive literature review on shear fracture dilation in-situ and in laboratory under moderate...

  Innehållstyp: Publikationer

• 2015:29 Technical Note, Quality Assurance in SKB’s Copper Corrosion Experiments

  01 juli 2015

  Report number: 2015:29 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Quality Assurance in SKB’s Copper Corrosion Experiments 2015:29 Author: Tim W. Hicks SSM 2015:29 SSM 2015:29 ... och korrigering av problemet. Systemövervakning, kon- troller och oförutsedda händelser bör byggas in i utformningen av experi- menten i syfte att säkerställa att värdefull data inte går förlorade. Det...

  Innehållstyp: Dokument

• 2015:11 Investigation of the Distribution of Phosphorus in Copper

  10 mars 2015

  .se Investigation of the Distribution of Phosphorus in Copper 2015:11 Author: Mattias Thuvander SSM 2015:11 SSM 2015:11 SSM perspective Background Copper alloyed with 30-100 ppm phosphorus ... phosphorus (P) is used as the corro- sion barrier of the canister which will be used for long term storage of spent nuclear waste for the KBS-3 concept proposed by SKB. The reason to add 30-100 ppm P is its...

  Innehållstyp: Dokument

• 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

  17 november 2015

  Assessment of data and criteria for cladding burst in loss-of-coolant accidents 2015:46 Author: Ali R. Massih Lars Olof Jernkvist SSM 2015:46 SSM 2015:46 SSM perspective Background In accident ... accident conditions in nuclear power plants it is plausible that the fuel rods are damaged due to high temperatures and pressure difference over the cladding. In analytical tools used for predicting fuel...

  Innehållstyp: Dokument

• 2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects

  10 mars 2015

  stralsakerhetsmyndigheten.se SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects 2015:10 Authors: Nadezhda Gotcheva ... organisational performance and safety culture in the nuclear industry have developed during past years. However, large projects have unearthed challenges in the field of Human-Technology-Organisation which have...

  Innehållstyp: Dokument

• 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