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02:53 SFR 1 Vault Database
David Savage, Mike Stenhouse SKI English...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems
The Swedish Radiation Safety Authority’s (SSM) experience is that there is a need to develop evaluation methods in parallel with the development of control rooms in conjunction with construction modifications and other changes. This includes more indepth analysis of the methods used today. Another aspect is that conventional methods of evaluating control rooms and issues need to be...
Innehållstyp: Publikationer -
2015:20 The effects of mild, acute hypoxia on cognitive performance
Room air with reduced oxygen levels that prevent materials to ignite and combust is a cost-effective and increasingly popular fire prevention method. For system safety reasons, the effects of hypoxia, that is, the lack of sufficient oxygen (that is, less than 21% oxygen which is the approximate oxygen level of normal air), on cognitive performance of persons working under such conditions are...
Innehållstyp: Publikationer -
99:46 Elements of a Regulatory Strategy for the Consideration of Future Human Actions in Safety Assessments
R. D. Wilmot, S. M. Wickham, D. A. Galson SKI English...
Innehållstyp: Publikationer -
00:54 Djupförvar för långlivat låg- och medelaktivt avfall i Sverige (SFL 3-5)
Neil Chapman, Michael Apted, Fred Glasser, John Kessler, Clifford Voss SKI Svenska...
Innehållstyp: Publikationer -
91:18 The CALIBRE Source-Term Code: Technical Documentation for Project-90
P. Robinson, K. Worgan SKI English...
Innehållstyp: Publikationer -
98:29 Design Basis for the Copper/Steel Canister, Stage four, Final Report
W. H. Bowyer SKI English...
Innehållstyp: Publikationer -
99:18 SKI:s och SSI:s granskning av SKB:s systemredovisning i FUD-program 98
SKI Svenska...
Innehållstyp: Publikationer -
2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
Innehållstyp: Publikationer