Rapporter

Din avgränsning ger 372 träffar.

• 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

• 2020:15 Strålskyddsåtgärder vid radiologiska nödsituationer

  I den här rapporten redovisar Strålsäkerhetsmyndigheten (SSM) planeringsunderlag för strålskyddsåtgärder vid radiologiska nödsituationer i samband med händelser i beredskapskategori 4. Händelser i beredskapskategori 4 omfattar händelser i verksamheter med joniserande strålning som inte bedrivs på en bestämd plats samt antagonistiska...

  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

• 2020:13 Core data Research at Uppsala University

  SSM perspective Background This project is to support a research group at Uppsala University in the research field of nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data libraries are used in different applications such as, nuclear...

  Innehållstyp: Publikationer

• 2020:11 Competency based assessments of Nuclear Power Plant controlroom operators

  Experiences of development and first operational methodological and technical demonstrator application...

  Innehållstyp: Publikationer

• 2020:07 Fibre Clogging in Nuclear Power Plants

  SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to  out foreign material suspended in the cooling water so this material does not reach the reactor. After the 1992 event at Barsebäck nuclear power plant when the strainers of the emergency cooling system was clogged due to fibers in the cooling water,...

  Innehållstyp: Publikationer