Din avgränsning ger 276 träffar.
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2017:33 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – dose assessment, Kd-values, and safety analysis methodology
Main review phase...
Innehållstyp: Publikationer -
1997:05 SKI SITE-94
The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...
Innehållstyp: Publikationer -
96:41 SKIs utvärdering av SKBs FUD-program 95
Sammanställning av remissvar...
Innehållstyp: Publikationer -
96:48 SKIs utvärdering av SKBs FUD-program 95
Gransknings-PM...
Innehållstyp: Publikationer -
96:49 SKIs utvärdering av SKBs FUD-program 95
Sammanfattning och slutsatser...
Innehållstyp: Publikationer -
1990:18 Some Estimates of the Total NuclideInventory in the Year 2100 from Swedish Nuclear Power Production
The total nuclide inventory in spent fuel from the swedish nuclear power programme has been estimated for three cases. All reactors were arrumed to operate until the year 2010 and then shut down simultaneously. All fuel used was assumed to be based on enriched natural uranium. The reactors were assumed to shut down after 25 years of commercial operation, but not later than in the year 2010.
Innehållstyp: Publikationer -
2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Innehållstyp: Publikationer -
2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models
In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...
Innehållstyp: Publikationer -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
Innehållstyp: Publikationer -
2011:16 Modelling of ultrasonic testing of cracks in cladding
During the last two decades, SSM has supported research to develop a model for the non-destructive test situation based on ultrasonic technique. Such a model is important in many ways, for example to supplement and plan experimental studies and to perform parametric studies in qualification situation. Modeling can be a useful tool when the inspection system shall be technically justified.
Innehållstyp: Publikationer