Filtered generated 755 hits.
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2005:21 DECOVALEX III PROJECT Thermal-Hydrological Modeling of the Yucca Mountain Project Drift Scale Test
Robin N. Datta with contributions from Sebastia Olivella, Claudia Gonzalez, Antonio Gens, Miguel Luna, Ronald T. Green, Scott L. Painter SKI English...
Content type: Publications -
2005:24 DECOVALEX III/BENCHPAR PROJECTS Implications of Thermal-Hydro-Mechanical Coupling on the Near-Field Safety of a Nuclear Waste Repository
L. Jing, T.S. Nguyen SKI English...
Content type: Publications -
02:21 (SSI 2002:12) Formulation and Presentation of Risk Assessments to Address Risk Targets for Radioactive Waste Disposal
R. D. Wilmot SKI English...
Content type: Publications -
2005:65 Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Cos RD&D Programme 2004
SKI English...
Content type: Publications -
02:02 R2/R0-WTR Decommissioning Cost Comparison and Benchmarking Analysis
Dr. Geoff Varley, Chris Rusch SKI English...
Content type: Publications -
02:53 SFR 1 Vault Database
David Savage, Mike Stenhouse SKI English...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
Content type: Publications