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Din avgränsning ger 28 träffar.

• 2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants

  component installed can function safely in the intended environment. Cables are among the most common components in a nuclear power plant and are required to function during normal operation as well as in the ... the event of an accident. There is a need within the nuclear industry for methodologies which can facilitate on-site measurement for condition monitoring, while having the capability to provide non-destructive...

  Innehållstyp: Publikationer

• 2021:10 Establishment and use of attention values in environmental fatigue assessments

  reach their original technical design life, re-assessment of the fatigue life of structural components is needed for safe long term operation (LTO). In these re-assessments one must consider that new knowledge ... life must be considered. One common method to verify the fatigue life of structural components subjected to an LWR coolant environment is to use so-called attention values. This simplistic method is beneficial...

  Innehållstyp: Publikationer

• 2021:03 Updated radiological risk assessment for the “Radon” type surface disposal facility in Chisinau, Moldova

  Sweden and the Republic of Moldova in nuclear and radiological safety and security has been ongoing since 2010, focusing on activities aimed at strengthening the institutional capacity of the National Agency ... Agency for Regulation of Nuclear and Radiological Activities in Moldova (NARNRA) as well as infrastructure development in radioactive waste management, handling and treatment at the Radioactive Waste Management...

  Innehållstyp: Publikationer

• 2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling

  SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential ... induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs suddenly and often unexpectedly. In order to study the crack initiation and growth...

  Innehållstyp: Publikationer

• 2021:04 Calibration of models for cladding tube high-temperature creep and rupture in the FRAPTRAN-QT-1.5 program

  closely. One aspect that is currently being studied in several research projects is the risk of release of fragmented fuel into the primary coolant in case of an accident. This risk depends on complex conditions ... conditions where one is the possibility and size of a rupture of the fuel rod cladding tube. This present report describes improvements to the FRAPTRAN-1.5 version extended by Quantum Technologies AB, regarding...

  Innehållstyp: Publikationer

• 2021:05 Cladding tube rupture under LOCA: Data and models for rupture opening size

  closely. One aspect that is currently being studied in several research projects is the risk of release of fragmented fuel into the primary coolant in case of an accident. This risk depends on complex conditions ... the possibility and size of a rupture of the fuel rod cladding tube. The work presented in this report is part of a larger endeavor to update the computer codes that SSM disposes of through Quantum Technologies...

  Innehållstyp: Publikationer

• 2021:20 Effects of additives on UO2 fuel behavior: expanded edition

  Safety Authority (SSM) follows the development of nuclear fuel closely. Fuel with additives like chromia and gadolinia is used in Swedish reactors and fuel with even better thermal and mechanical properties ... is an in-depth study of data and models regarding the impact of additives on the properties of uranium dioxide fuel for light water reactors. The report is an update and expansion of the study of additives...

  Innehållstyp: Publikationer

• 2021:09 Mechanisms important for material modelling in weld residual stress analysis

  SSM perspective Background The prediction of weld residual stresses (WRS) is very complex as many mechanisms and phenomena influence the development of WRS during welding. For accurate prediction, the ... models used are essential and must be able to describe the material response of the weldment constituents. For example, selection of a material model should only depend on material behaviour and not on other...

  Innehållstyp: Publikationer
• 11 mars 2021

  Resultat av LOT-tester i linje med tidigare kunskap

  Strålsäkerhetsmyndigheten (SSM) har sammanställt en granskningsrapport av Svensk Kärnbränslehantering AB:s (SKB) senaste fas i det så kallade LOT-försöket. ... Svensk Kärnbränslehantering AB:s (SKB) senaste fas i det så kallade LOT-försöket. LOT (Long-term test of buffer material) är långtidsfältförsök i syfte att studera vad som sker under den initiala utvecklingen...

  Innehållstyp: Nyheter

• Poddavsnitt 16: Så fungerar oberoende härdkylning - stor säkerhetshöjning av svensk kärnkraft

  Oberoende härdkylning är en ny säkerhetsfunktion som finns installerat på alla svenska kärnkraftsreaktorer. Enkelt uttryckt kan man säga att det handlar om ... installerat på alla svenska kärnkraftsreaktorer. Enkelt uttryckt kan man säga att det handlar om ett system som ska kunna kyla bränslet i reaktorn om alla andra säkerhetsfunktioner av någon anledning har slutat...

  Innehållstyp: Artiklar