Publikationer

Din avgränsning ger 6 träffar.

• 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

• 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

• 2020:02 Models for axial gas flow and mixing in LWR fuel rods

  SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow to the plenum volume at the top of the fuel rod. In high burnup fuel, this axial flow to the...

  Innehållstyp: Publikationer