SAFIR2010 - Interim Seminar 2009
Presentations:
Opening of
the Seminar
Lasse Reiman, STUK - Radiation and Nuclear Safety Authority,
Finland
Views from the EU, Simon Webster
Overview of
SAFIR2010
Eija Karita Puska, VTT
Research area 1: Organisation and human factors
Safety management and organisatorial learning (MANOR):
Safety culture and
organizational learning,
Pia Oedewald, VTT
Expert work in safety critical environment (SAFEX):
Knowledge sharing in
interorganizational context, Eerikki Mäki, HUT
Research area 2: Automation and control room
Model-based safety evaluation of automation systems (MODSAFE):
Summary report,
Janne Valkonen, VTT
Summary report, Hannu Harju, VTT
Operator practices and human-system interfaces in
computer-based control stations (OPRACTICE):
Designing large-screen
overview displays for nuclear power plant control rooms, Jari
Laarni, VTT
Research area 3: Fuel and reactor physics
Development and validation of fuel performance codes (POKEVA):
LOCA Test Simulation with
FRAPTRAN-GENFLO, Jan-Olof Stengård, VTT
Tri-dimensional core transient analysis methods (TRICOT):
The porous medium model
PORFLO for 3D two-phase flow and its application to BWR fuel bundle
simulations, Mikko Ilvonen, VTT
Total reactor physics analysis system (TOPAS):
Development of the PSG2 /
Serpent Monte Carlo Reactor Physics Burnup Calculation Code,
Jaakko Leppänen, VTT
Research area 4: Thermal hydraulics
Numerical modelling of condensation pool (NUMPOOL):
Summary report,
Timo Pättikangas, VTT
Improved thermal hydraulic analyses of nuclear reactor and
containment (THARE):
Validation of APROS’ Upper tie
plate CCFL correlation in VVER 440 Geometry, Joona Kurki, VTT
CFD modelling of NPP horizontal and vertical steam generators (SGEN):
CFD modeling of horizontal
steam generators, Timo Pättikangas, VTT
Improvement of PACTEL facility simulation environment (PACSIM):
Summary report,
Antti Rantakaulio, LUT
Condensation experiments with PPOOLEX facility (CONDEX):
PPOOLEX Wall Condensation
Experiments, Markku Puustinen, LUT
Large break loss of coolant accident test facility study (LABRE) and
Large break loss of coolant accident test rig (LABRIG):
Summary report,
Heikki Purhonen, LUT
Research area 5: Severe accidents
Release of radioactive materials from a degrading core (RADECO):
Formation of organic iodide on
painted surface, Tommi Kekki, VTT
Primary circuit chemistry of fission products (CHEMPC):
Radiolytic oxidation of
iodine in containment conditions, Teemu Kärkelä, VTT
Core melt stabilization (COMESTA):
HECLA Experiments on
Melt–Concrete Interactions, Tuomo Sevón, VTT
Hydrogen risk in containments and particle bed issues (HYRICI):
STYX dry-out heat flux
testing with lateral coolant inflow, Eveliina Takasuo, VTT
Research area 6: Structural safety of reactor circuit
Risk-informed inspections of piping (PURISTA):
Summary report, Kaisa
Simola, VTT
Fatigue of primary circuit components (FATE):
Cyclic behaviour and fatigue
design criteria for stainless steel, Jussi Solin, VTT
Water chemistry and oxidation in the primary circuit (WATCHEM):
Development and verification
of in situ techniques to study oxidation and water chemistry effects in
the primary circuit, Timo Saario, VTT
Monitoring of the structural integrity of reactor circuit (RAKEMON):
Ultrasonic inspection
simulations with CIVA version 8, Ari Koskinen, VTT
Fracture assessment of reactor circuit (FRAS):
Simulation of thermal striping
in a HDR experiment, Antti Timperi, VTT
Influence of material, environment and strain rate on environmentally
assisted cracking of austenitic nuclear materials (DEFSPEED):
Strain localisation in
sensitised Type 304 stainless steel in simulated BWR-environment,
Ulla Ehrnstén, VTT
Research area 7: Construction safety
Service life management system of concrete structures in nuclear
power plants (SERVICEMAN):
Service Life Management
System of Concrete Structures in Nuclear Power Plants,
Erkki Vesikari, VTT
IMPACT2010 (IMPACT) and Structures under soft impact (SUSI):
Summary report (combined presentation), Juha Kuutti, VTT
Research area 8: Probabilistic safety analysis (PSA)
Challenges in risk-informed safety management (CHARISMA):
Reliability analysis of
digital I&C systems in nuclear power plants, Ilkka Karanta,
VTT
Implementation of quantitative fire risk assessment in PSA (FIRAS):
Estimation of pyrolysis model
parameters for condenced phase materials, Anna Matala, VTT
Extreme weather and nuclear power plants (EXWE):
Abrupt climate change and
nuclear power plant safety, Natalia Pimenoff, FMI