Visar 4461 sökträffar på ””
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2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
Innehållstyp: Publikationer -
2019:24 SSM's external experts' review of SKB's analysis of long-term safety of 1BMA (SFR)
SSM perspective Background Fractures in the concrete barrier of the rock vault 1BMA in the final repository for low and intermediate level waste (SFR) have been observed. The Swedish Radiation Safety Authority (SSM) enforced Swedish Nuclear Fuel and Waste Management Company (SKB) to assess the long-term radiological consequences of 1BMA (SSM2015-2432-26) given the present state of the rock...
Innehållstyp: Publikationer -
2007:45 Icke-spridning och kärnämneskontroll
Det kompendium som nu föreligger kommer att användas både inom och utom landet som kursmaterial vid utbildningar. Det är delvis ett resultat av ESARDA:s (European Safeguards Research and Development Association) arbetsgrupp TKM (Training and knowledge management) som årligen utbildar studenter från hela Europa. Avsikten är även att använda det i samband...
Innehållstyp: Publikationer -
2003:46 Cerenkov Characteristics of PWR Assemblies Using a Prototype DCVD With a Back-Illuminated CCD
Canadian and Swedish Safeguard Support Programs J.D. Chen, A.F. Gerwing, R. Maxwell, M. Larsson, K. Axell, L. Hildingsson, B. Lindberg, E. Sundkvist. November 2003 SKI English...
Innehållstyp: Publikationer -
2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report
The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...
Innehållstyp: Publikationer -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
Innehållstyp: Publikationer -
2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA
No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...
Innehållstyp: Publikationer -
2010:03 Forskningsstrategi 2010-2014
Strålsäkerhetsmyndighetens uppdrag omfattar frågor om skydd av människors hälsa och miljön mot skadlig verkan av joniserande och icke-joniserande strålning, säkerhet i kärnteknisk verksamhet samt nukleär icke-spridning. För att myndigheten ska kunna utföra uppdraget behöver ny kunskap kontinuerligt tillföras verksamheten. Genom...
Innehållstyp: Publikationer -
2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials
SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary stresses for estimating the safety margin against rupture (measured by the J-integral) for the type...
Innehållstyp: Publikationer -
2009:15 Improvement and Validation of Weld Residual Stress Modelling Procedure
Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...
Innehållstyp: Publikationer