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  • Appendix 3 – Dispersion and Dose Calculations

    Simon Karlsson Date: November 2023 Report number: 2023:05e ISSN: 2000-0456 Available at www.ssm.se SSM 2023:05e Date: November 2023 Report number: 2023:05e ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten ... describes the dispersion and dose calculations performed by the Swedish Radiation Safety Authority (SSM) for the purpose of assessing the radiological consequences of fallout from a nuclear explosion.

    Innehållstyp: Dokument
  • 02:4 Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing

    performed a research project on this topic. The purpose The purpose of the work has been to produce a background material for planning and management of qualification work on components inside the containment ... the international development will be reviewed. Based on this a decision on possible needs for complementary studies will be taken. Effects on SKI's work The purpose of the work is to provide background...

    Innehållstyp: Dokument
  • 2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach

    accident reminders on different aspects of safety management in the nuclear context. reporting, and measurement of safety. The results give interesting insights and important reminders on different aspects ... accident reminders on different aspects of safety management in the nuclear context. reporting, and measurement of safety. The results give interesting insights and important reminders on different aspects...

    Innehållstyp: Publikationer
  • 1997:12 Study of International Published Experiences in Joining Copper and Copper-alloys

    final storage of high level nuclear waste. However, the decision on which material and which joining process to be used has to be based on the design criterions. The welding procedure has to be qualified ... final storage of high level nuclear waste. However, the decision on which material and which joining process to be used has to be based on the design criterions. The welding procedure has to be qualified...

    Innehållstyp: Publikationer
  • 95:58 Reliability of Piping System Components. Volume 1: Piping Reliability – A Resource Document for PSA Applications (pdf 436 kB)

    Assessment (SKI/RA) SKI/RA-027/95 Ralph Nyman & Stig Erixon Swedish Nuclear Power Inspectorate, Dept. RA S-106 58 Stockholm, Sweden Bojan Tomic ENCONET Consulting GesmbH Hansi Niese Weg 19 A-1130 Vienna ... necessarily coincide with those of the SKI. iSKI Report 95:58 SUMMARY 1. Background Reflecting on older analysis practices, passive component failures seldom receive explicit treatment in PSA. To...

    Innehållstyp: Dokument
  • Spricktillväxt i LAS - Martin Bjurman.pdf

    MPa√m i plåt med svavelhalt i övre änden av låga S-halter MÅL 2019-11-05SSM strålsäkerhetsdagar 2019, 3 Att studera SCC i tankstål med mellanhög S-halt (0.011%) I BWR-NWC-miljö vid K= 50-70 MPa mmed ... (arkivmaterial) ● ASTM 533 Gr. B Class 1 med 0.011% S • En konservativ men relevant S-halt för svenska reaktortryckkärl Element C Mn Si Ni Cr Mo S P Cu Sn Co Wt.% 0.185 1.365 0.275 0.59 0.12 0.525 0...

    Innehållstyp: Dokument
  • 95:61 Reliability of Piping System Components. Volume 4: The Pipe Failure Event Database (pdf 371 kB)

    Bengt Lydell 3 Swedish Nuclear Power Inspectorate, Department of Plant1 Safety Assessment (SKI/RA), S-106 58 Stockholm, Sweden ENCONET Consulting GesmbH2 Hansi Niese Weg 19 A-1130 Vienna, Austria ... database on worldwide piping system failure events in the nuclear and chemical industries. The subject report includes Phase 2 results. 2. Implementation Available public and proprietary databases on piping...

    Innehållstyp: Dokument
  • 1994:15 Aging Degradation of Concrete Structures in Nuclear Power Plants

    1822 kB ... S K I R e p o r t 9 4 : 1 5 A g i n g D e g r a d a t i o n o f C o n c r e t e S t r u c t u r e s i n N u c l e a r P o w e r P l a n t s M a r k J . D o a n d A l a n D . C h o c ... c k i e S e p t e m b e r 1 9 9 4 I S S N 1 1 0 4 - 1 3 7 4 I S R N S K I - R - - 9 4 / 1 5 - - S E SKI Report 94: 15 Aging Degradation of Concrete Structures in Nuclear Power Plants Mark...

    Innehållstyp: Dokument
  • 2017:10 Inverkan av ligament på spricköppning och K-faktor vid IDSCC

    3137 ... 2017:10 Författare: Daniel Andersson Daniel Mångård Jens Gunnars Forskning SSM 2017:10 SSM 2017:10 SSM perspektiv Bakgrund Visuell teknik (VT) är en av de metoder som används för provning ... mellan restspänning och primärspänning för sprickor med och utan ligament. SSM 2017:10 Projekt information Kontaktperson SSM: Erik Strindö Referens: SSM2013-2194 2017:10 Författare: Daniel Andersson...

    Innehållstyp: Dokument
  • 95:59 Reliability of Piping System Components. Volume 2: PSA LOCA Data Base Review of Methods for LOCA Evaluation since the WASH-1400 (pdf 364 kB)

    Evaluation since the WASH-1400 Ralph Nyman & Stig Erixon Swedish Nuclear Power Inspectorate, Dept. RA S-106 58 Stockholm, Sweden Bojan Tomic & Helmut Wimmer ENCONET Consulting GesmbH, Hansi Niese Weg 19 ... report are those of the author(s) and do not necessarily coincide with those of the SKI. SKI Report 95:59 Rev. 1 i SUMMARYSUMMARY 1. 1. BackgroundBackground Reflecting on older analysis practices,...

    Innehållstyp: Dokument