Din avgränsning ger 2055 träffar.
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2015:38 Evaluation of fatigue in austenitic stainless steel pipe components
pipe components 2015:38 Author: Magnus Dahlberg, Dave Hannes, Thomas Svensson SSM 2015:38 SSM 2015:38 SSM perspective Background Transferability of experimental results obtained for smooth ... austenitic stainless steel, by performing fatigue experiments on a realistic welded austenitic stainless steel piping component. A particular focus is on high cycle fatigue and variable amplitude loading. Results...
Innehållstyp: Dokument -
00:42 Study of Defect Characteristics Essential for NDT Testing Methods ET, UT and RT
1522 kB ... S K I R e p o r t 0 0 : 4 2 R e s e a r c h S t u d y o f D e f e c t C h a r a c t e r i s t i c s E s s e n t i a l f o r N D T T e s t i n g M e t h o d s E T , U T a n d R T H ... e l i u s E l e n a Ö s t e r b e r g O c t o b e r 2 0 0 0 I S S N 1 1 0 4 – 1 3 7 4 I S R N S K I - R - 0 0 / 4 2 - S E S T A T E N S K Ä R N K R A F T I N S P E K T I O N S w e d i...
Innehållstyp: Dokument -
Barrier process report TR-14-04.pdf
calculations for the safety assessment (2) SDM-PSU Forsmark Site description of the SFR area at Forsmark on completion of the site investigation Bilaga BAT Utbyggnad av SFR ur ett BAT-perspektiv Bilaga ... application to extend SFR. Most of the material in the report was contributed by selected experts in the field; see Section 1.7 for a complete list of contributors. The report has been reviewed by; Jordi Bruno...
Innehållstyp: Dokument -
2014:08 Technical Note, Review of Long-Term Redox Evolution of Groundwater and Potential Influence of Oxygenated Glacial Meltwater in SR-Site
in SR-Site Main Review Phase Authors: Jude McMurry F. Paul Bertetti SSM perspektiv Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen ... slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta information i avgränsade frågor. I SSM:s Technical note-serie rapporteras...
Innehållstyp: Dokument -
02:51 Nuclear Criticality Safety Assessment Using the SCALE Computer Code Package A demonstration based on an independent review of a real application
Nuclear Criticality Safety Assessment Using the SCALE Computer Code Package A demonstration based on an independent review of a real application Dennis Mennerdahl June 1998 ISSN 1104–1374 ISRN SKI-R-02/51-SE ... Nuclear Criticality Safety Assessment Using the SCALE Computer Code Package A demonstration based on an independent review of a real application Dennis Mennerdahl E Mennerdahl Systems Starvägen 12 SE-183...
Innehållstyp: Dokument -
2008:57 Discrete Feature Model (DFM) User Documentation
SKI Perspective Background SKI engages consultants to perform scientific and technical assessments in order to obtain a good scientific and technical basis for monitoring the Swedish nuclear fuel and ... or piecewiseplanar surface, described at each point on its surface by effective 2D parameters of transmissivityξ T( ), storativity ξ S( ), and transport aperture ξ b( ). Typically these parame...
Innehållstyp: Dokument -
2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report
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. Background The MERIT project ... more of a research code than a regulatory tool. Effects on SSM supervisory and regulatory task The results of this project will be used by SSM for the assessment of detec- ted cracks in nuclear piping...
Innehållstyp: Dokument -
2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures
Authors: Peter Segle Jessica Strömbro Alexander Wulff Johan Kölfors Albin Larsson Robert Persson SSM perspective Background The design codes for anchorage of equipment in concrete structures have ... 349-06 code open up today for a more detailed analysis where the beneficial impact of rein- forcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly...
Innehållstyp: Dokument -
2004:11 An Applied Study of the Storage for Old Intermediate Level Waste at the Studsvik Site (pdf 389 kB)
Background The nuclear power utilities must under the so-called Studsvik Act (the complete name is the Act on the Financing of the Management of Certain Radioactive Waste etc. (1988:1597)) contribute with 0,15 ... Old Intermediate Level Waste (hereafter denoted AT from Swedish “det Aktiva Tråget”). Moreover, SKI´s standpoint is that all measures that enhance the overall quality of the calculation of fees to the fund...
Innehållstyp: Dokument -
2022:02 APRI-10 - Slutrapport
Pasi 7) 1) SSM, 2) Vattenfall, 3) RAB, 4) KTH, 5) IPM RAS, 6) EREC, 7) Chalmers Rapportnummer: 2022:02 ISSN: 2000-0456 Tillgänglig på: www.ssm.se SSM 2022:02 SSM 2022:02 SSM perspektiv Bakgrund ... Bakgrund Strålsäkerhetsmyndigheten (SSM) har sedan början på 1990- talet finansierat forskning inom svåra haverier, då dåvarande SKI finansiellt bidrog till en professur och utvecklandet av avdelningen...
Innehållstyp: Dokument