Publikationer

Din avgränsning ger 209 träffar.

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

  SSM perspective Background As Swedish NPPs 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 has shown that environmental effects on fatigue life must be considered. One common method to verify the fatigue life of structural components...

  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 constitutive material 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...

  Innehållstyp: Publikationer

• 2021:07 Scenariourval i HFE-processen Arbetssätt och kriterier vid utvärdering av konstruktionens anpassning till människans förmåga

  SSM perspektiv Bakgrund På en kärnteknisk anläggning genomförs under dess livstid så kallade anläggningsändringar i syfte att åtgärda identifierade brister, eller för att av andra skäl modernisera eller förbättra anläggningens konstruktion. Vid anläggningsändringar som påverkar arbetsuppgifter som har betydelse...

  Innehållstyp: Publikationer

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

  SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance 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 were one is the possibility and size of a rupture of the fuel rod...

  Innehållstyp: Publikationer

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

  SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance 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 where one is the possibility and size of a rupture of the fuel rod...

  Innehållstyp: Publikationer

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

  SSM perspective Background Bilateral cooperation between 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 for Regulation of Nuclear and Radiological Activities in Moldova (NARNRA) as well as infrastructure development in radioactive...

  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 to study and further understand the mechanism for environmentally induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs...

  Innehållstyp: Publikationer

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

  SSM perspective Background As the nuclear power plants are ageing, it is important to verify that every 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 event of an accident. There is a need within the nuclear industry for...

  Innehållstyp: Publikationer

• 2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint

  SSM perspective Background Leak-before-break (LBB) piping assessments have shown that piping systems can withstand long through-wall cracks before pipe rupture is expected. This is somewhat because pipe ends are restrained. In LBB assessments analyses are often performed for a pipe segment uncoupled from the piping system, as pipe ends are assumed unrestrained. This assumption is conservative...

  Innehållstyp: Publikationer

• 2020:12 Assessment of the QT-COOL coolant channel module against the PBF RIA 1-2 experiment

  SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. This ensures a possibility...

  Innehållstyp: Publikationer