Filtered generated 57 hits.
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2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents
In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...
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2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
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2016:28 Fatigue fracture surface characterization and investigation
1091 kB...
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2016:25 Licensing of safety critical software for nuclear reactors
2040 kB...
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2016:13 Spännarmerade betongkonstruktioner vid kärntekniska anläggningar
2789 kB...
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2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity
8859 kB...
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2016:20 A standardized Swedish naming convention for radiation therapy
The national reference group SSM English...
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2016:12 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – engineered barriers, engineering geology and chemical inventory
3808 kB...
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2016:03 Laseranrikning av uran ur ett icke-spridningsperspektiv
1908 kB...
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2016:10 Utredning om funktions- och leveranskontroller av radiologisk utrustning
1783 kB...
Content type: Documents