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  • 2013:08 Licensing of safety critical software for nuclear reactors

    organisations –Revision 2013 SSM 2013:08 Background This report is the 5th revision of the report. The task force was formed in 1994 as a group of experts on safety critical software. The members ... members come from regulatory authorities and/or their technical support organization. Bo Liwång, SSM, has been a member since the work started in 1994. For full information of the historical background...

    Innehållstyp: Dokument
  • 2001:21 Work in Support of Biosphere Assessments for Solid Radioactive Waste Disposal. 1. Performance Assessments, Requirements and Methodology; Criteria for Radiological Environmental Protection

    to assess how the recent Swedish regulatory developments and resulting criteria impose requirements on what should be included in a performance assessment (PA) for the SFR low and medium level waste repository ... environment, for use in Sweden. This is achieved through a review of various approaches used in other fields. SAMMANFATTNING: Syftet med den första delen av rapporten är att analysera vilka krav som ställs...

    Innehållstyp: Dokument
  • 2016:02 Technical Note, An updated review of the creep ductility of copper including the effect of phosphorus

    effect of phosphorus 2016:02 Author: Kjell Pettersson SSM 2016:02 SSM 2016:02 SSM:s perspektiv Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehanter- ing AB:s (SKB) ansökningar ... 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
  • 2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility

    5383 ... nuclear fuel with regard to copper creep ductility 2017:18 Author: Calle Engman SSM 2017:18 SSM 2017:18 SSM perspective Background For final storage of spent nuclear fuel it is suggested by ... study the containment ability of canisters copper shell by means of creep brittleness. The safety SSM 2017:18 function of the copper shell is to provide an approximately 50 mm thick corrosion barrier...

    Innehållstyp: Dokument
  • 2009:02 Screening calculations for radioactive waste releases from non-nuclear facilities

    Radia- tion Safety Authority, SSM. The conclusions and viewpoints presented in the report are those of the author/authors and do not necessarily coincide with those of the SSM. Summary A series of screening ... calculations follow the philosophy of the IAEA’s safety guidance starting with a simple assess- ment based on very conservative assumptions which may be iteratively refined using progressively more complex models...

    Innehållstyp: Dokument
  • 2013:16 Technical Note, Assessment of PWR fuel depletion and of neutron multiplication factors for intact PWR fuel copper canisters – main review phase

    fuel copper canisters Main review phase Author: Dennis Mennerdahl 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 kon- sulter uppdrag för att inhämta information och göra expertbedömningar i avgränsade frågor. I...

    Innehållstyp: Dokument
  • 2024:09 General data in accordance with the requirements in Article 37 of the Euratom Treaty

    Report 2024:09 Date: May 2024 Report number: 2024:09 ISSN: 2000-0456 Available at www.ssm.se SSM 2024:09 Date: May 2024 Report number: 2024:09 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten ... 2024:09 SSM perspective This report has been completed by the Swedish Radiation Safety Authority, SSM, mainly based on information provided by the license holder, Cyclife Sweden AB. SSM has controlled...

    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
  • 2005:29 DECOVALEX III PROJECT Thermal-Hydro-Mechanical Coupled Processes in Safety Assessments

    laboratory experiments. DECOVALEX II, started in 1996, built on the experience gained in DECOVALEX I by modeling larger tests conducted in the field. DECOVALEX III, started in 1999 following the completion ... thermal-hydrologic-mechanical (THM) coupling on the performance of the near-field of a nuclear waste repository (BMT1); b) the effect of upscaling THM processes on the results of performance assessment (BMT2);...

    Innehållstyp: Dokument