Rapporter

Din avgränsning ger 251 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

• 2021:02 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

• 2020:07 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

• 2020:05 General data in accordance with the requirements in Article 37 of the Euratom Treaty

  Decommissioning of the nuclear reactors Ringhals 1 and Ringhals 2 in Sweden...

  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

• 2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study

  SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...

  Innehållstyp: Publikationer

• 2019:23 Participation in the European Committee for Standardization's workshop regarding civil structures

  SSM perspective Background During the period 2014-2018, a CEN1 workshop (Phase 2 Prospective Group 3 civil works) have been carried out. The aim of the workshop is to provide a base founded on the French standard in order to be able to establish a possible future European standard for the design of civil structures at nuclear power plants. The workshop has identied which additional...

  Innehållstyp: Publikationer

• 2019:20 Assessment of structures subject to concrete pathologies (ASCET), phase 3

  SSM perspective Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to ageing of...

  Innehållstyp: Publikationer