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Visar 3352 sökträffar på ”SSM’s Scientific Council on Electromagnetic Fields”

• 2006:30 Benchmarking – a validation of UTDefect

  01 januari 2006

  results show good correlation to experimental data in most of the cases. It also gives us information on some cases where continuous development is necessary. Project information Responsible for the project ... Spherical cavity 12 CONCLUDING REMARKS 13 REFERENCES 14 Summary New and stronger demands on reliability of used NDE/NDT procedures and methods have stimulated the development of simulation tools...

  Innehållstyp: Dokument

• 2015:25 Design Guide for Nuclear Civil Structures (DNB)

  01 juni 2015

  Jovall, Johan Kölfors, Patrick Andersson, Jan-Anders Larsson Sven Thelandersson SSM 2015:25 SSM 2015:25 SSM perspective Background Until 2010, the National Swedish Building Code (BKR, BBK) has ... Authority (SSM) and the Swedish licen- sees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes,...

  Innehållstyp: Dokument

• 02:09 SKI:s yttrande över SKB:s redovisning av FUD-program 2001 (pdf 1,66 Mb)

  01 januari 2002

  använt kärnbränsle och kärnavfall (prop. 1980/81:90, bilaga 1, s. 319, prop. 1983/84:60, s. 38, prop. 1997/98:145, s. 381, prop. 1992/93:98, s. 29 samt näringsutskottets betänkanden 1988/89:NU31 och 1989/90:NU24): ... fylla något egentligt syfte att ytter- ligare reglera denna fråga i kärntekniklagen (prop. 1997/98:145, s. 381 fjärde stycket). 2.6 Systemanalys Remissinstansernas synpunkter Kungliga tekniska högskolan...

  Innehållstyp: Dokument

• 01:20 SKI:s yttrande över SKB:s kompletterande redovisning till FUD-program 98

  01 januari 2001

  261 kB...

  Innehållstyp: Dokument

• 00:39 SKI:s och SSI: gemensamma granskning av SKB:s Säkerhetsrapport 97. Granskningsrapport

  01 januari 2000

  311 kB...

  Innehållstyp: Dokument

• 2017:13 Monte Carlo patient-specific pre-treatment QA system for volumetric modulated arc therapy

  increased. Current practices in Sweden normally compare the delivered dose with the planned dose based on measurements with different methods, for instance: portal dosimetry, point dose verification and/or ... and the performing of retrospective calculations and analysis. The Swedish Radiation Safety Authority's intention with the project is to contribute to a safer radiotherapy. Furthermore, the authority would...

  Innehållstyp: Publikationer

• 2015:53 Ductile tearing – Micromechanical analyses and experimental study

  experimental results in can be drawn with regard to fracture toughness and the decreasing influence on the J-integral for increasing primary load. The predictions made here also show an improvement when ... technique is a sound approach in studying the effects from residual stresses on ductile fracture at low primary loads. Tobias Bolinder SSM English In this report, the project "Ductile Tearing-Micromechanical analyses...

  Innehållstyp: Publikationer

• 2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions

  The results are compared with experimental data on cladding rupture strain, temperature and pressure. The effects of heating rate and rod internal pressure on the rupture strain are evaluated by systematic ... alloy, for which no definite constitutive relation is yet available. Tero Manngård and Ali R. Massih SSM English We present a unified model for calculation of zirconium alloy fuel cladding rupture during...

  Innehållstyp: Publikationer

• 2012:49 Hydrogeological characteristics of sites for low- and intermediate-level waste disposal

  the magnitude and anisotropy of effective hydraulic conductivity on various scales. However, prediction of the consequences is dependent on complex fracture-network models, and these have not been presented ... than the Forsmark-SFR site; however, estimates are within roughly an order of magnitude. Joel Geier SSM English The Forsmark area with its selected two sites and the Laxemar-Simpevarp area with its two sites...

  Innehållstyp: Publikationer

• 2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7

  08 maj 2014

  loss-of-coolant accident experiments 5, 6 and 7 2014:19 Authors: Tero Manngård Jan-Olof Stengård SSM perspective  Background  Loss of Coolant Accidents (LOCA) are among the most demanding ac­ cidents ... 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 subse­ quent release of...

  Innehållstyp: Dokument