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• 2017:36 Topical Peer Review 2017 Ageing Management Swedish National Assessment Report

  Executive summary The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years with the first starting in 2017. The member states, acting through the European Nuclear Safety Regulators Group (ENSREG), have

  Content type: Publications

• 2017:35 Review of paleo-, historical and current seismicity in Sweden and surrounding areas with implications for the seismic analysis underlying SKI report 92:3

  Abstract The report contains a review of the current state of knowledge on Swedish paleoseismic events, as well as information on the Swedish earthquake catalogue updated to early autumn 2016 and the revised Nordic earthquake catalogue (Fencat). It includes a section on the possibilities to assess

  Content type: Publications

• 2017:32 COMRAD – Comprehensive investigation of the performance of computed and digital radiography

  Background Within the industry, there has long been a need to replace the traditional X-ray film and its handling. These both for economic and environmental considerations. Both computed radiography and digital radiography offer many advantages over the traditional use of x-ray with film. However,

  Content type: Publications

• 2017:29 Evaluation of the simulation software CIVA for qualification purpose

  Background Modeling is an important tool within NDT, partly to develop and optimize testing technologies, but also within the Qualification Body’s activities to assess technical verifications and perform parameter studies. SSM has supported university research in the area for many years and, among

  Content type: Publications

• 2017:25 Evaluation of weld fatigue reduction in austenitic stainless steel pipe components

  Background The performed investigation is a continuation of the work performed in SSM 2015:38 where fatigue tests were performed on pressurized welded austenitic stainless steel piping components. The specimens were subjected to a realistic variable amplitude loading with mainly reversed bending

  Content type: Publications

• 2017:22 Effect of weld repairs on residual stresses in nickel base dissimilar metal welds

  Background The driving force for crack growth near welds in nuclear application piping may arise from weld residual stresses. Experience from nondestructive examination show that cracks in dissimilar metal welds are often found near weld repairs. The repair welding may affect the residual stresses

  Content type: Publications

• 2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents

  In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant

  Content type: Publications

• 2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2

  Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into

  Content type: Publications

• 2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending

  Background The case of a circumferential crack in a cylindrical bar has not been available in the ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known

  Content type: Publications

• 2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik

  Background Loss of Coolant Accidents (LOCA) are among the most demanding accidents that can happen in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of

  Content type: Publications