Citation: M. Cepin et B. Mavko, FAULT-TREE DEVELOPED BY AN OBJECT-BASED METHOD IMPROVES REQUIREMENTS SPECIFICATION FOR SAFETY-RELATED SYSTEMS, Reliability engineering & systems safety, 63(2), 1999, pp. 111-125
Citation: T. Dvorsek et al., SAFETY AND AVAILABILITY OF STEAM-GENERATOR TUBES AFFECTED BY SECONDARY-SIDE CORROSION, Nuclear Engineering and Design, 185(1), 1998, pp. 11-21
Citation: M. Cepin et B. Mavko, PROBABILISTIC SAFETY ASSESSMENT IMPROVES SURVEILLANCE REQUIREMENTS INTECHNICAL SPECIFICATIONS, Reliability engineering & systems safety, 56(1), 1997, pp. 69-77
Citation: R. Jordancizelj et B. Mavko, INFLUENCE OF SPECIFIC DATA ON A RESEARCH REACTOR PROBABILISTIC MODEL, Reliability engineering & systems safety, 52(1), 1996, pp. 55-63
Authors:
CIZELJ L
MAVKO B
RIESCHOPPERMANN H
BRUCKERFOIT A
Citation: L. Cizelj et al., PROPAGATION OF STRESS-CORROSION CRACKS IN STEAM-GENERATOR TUBES, International journal of pressure vessels and piping, 63(1), 1995, pp. 35-43
Citation: L. Cizelj et B. Mavko, ON THE RISK-BASED STEAM-GENERATOR LIFETIME OPTIMIZATION, Theoretical and applied fracture mechanics, 23(2), 1995, pp. 129-137
Citation: S. Petelin et al., ANALYSIS OF OPERATOR ACTIONS DURING THE ACCIDENT CAUSED BY TOTAL LOSSOF SECONDARY HEAT SINK, Nuclear Engineering and Design, 159(2-3), 1995, pp. 169-175
Citation: I. Parzer et al., FEED-AND-BLEED PROCEDURE MITIGATING THE CONSEQUENCES OF A STEAM-GENERATOR TUBE RUPTURE ACCIDENT, Nuclear Engineering and Design, 154(1), 1995, pp. 51-59
Citation: I. Parzer et al., VERIFICATION OF CCFL MODEL IN RELAP5 THERMAL-HYDRAULIC CODE, Zeitschrift fur angewandte Mathematik und Mechanik, 74(5), 1994, pp. 200000447-200000451
Citation: L. Cizelj et al., APPLICATION OF 1ST AND 2ND-ORDER RELIABILITY METHODS IN THE SAFETY ASSESSMENT OF CRACKED STEAM-GENERATOR TUBING, Nuclear Engineering and Design, 147(3), 1994, pp. 359-368
Citation: B. Sarler et al., MIXTURE CONTINUUM FORMULATION OF CONVECTION-CONDUCTION ENERGY-TRANSPORT IN MULTICONSTITUENT SOLID-LIQUID PHASE-CHANGE SYSTEMS FOR BEM SOLUTION TECHNIQUES, Engineering analysis with boundary elements, 11(2), 1993, pp. 109-117
Citation: I. Parzer et al., NONEQUILIBRIUM PROCESSES DURING THE SMALL BREAK LOSS-OF-COOLANT ACCIDENT IN NUCLEAR-POWER-PLANTS, Zeitschrift fur angewandte Mathematik und Mechanik, 73(7-8), 1993, pp. 200000732-200000736
Citation: B. Sarler et al., A BEM FORMULATION FOR MOMENTUM, ENERGY AND SPECIES TRANSPORT IN BINARY SOLID-LIQUID PHASE-CHANGE SYSTEMS, Zeitschrift fur angewandte Mathematik und Mechanik, 73(7-8), 1993, pp. 200000804-200000809
Citation: A. Stritar et al., UNCERTAINTY ANALYSIS OF THE LARGE BREAK LOSS-OF-COOLANT ACCIDENT, Zeitschrift fur angewandte Mathematik und Mechanik, 73(7-8), 1993, pp. 200000854-200000856
Citation: I. Tiselj et B. Mavko, HYDROGEN COMBUSTION DESCRIBED WITH INCOMPRESSIBLE-FLUID APPROXIMATION, Zeitschrift fur angewandte Mathematik und Mechanik, 73(6), 1993, pp. 619-623
Citation: B. Mavko et L. Cizelj, APPLICATION OF PROBABILISTIC FRACTURE-MECHANICS IN STEAM-GENERATOR PROBLEM MANAGEMENT, Zeitschrift fur angewandte Mathematik und Mechanik, 73(4-5), 1993, pp. 462-465
Citation: B. Mavko et al., APPLICATION OF CODE SCALING, APPLICABILITY AND UNCERTAINTY METHODOLOGY TO LARGE BREAK LOCA ANALYSIS OF 2 LOOP PWR, Nuclear Engineering and Design, 143(1), 1993, pp. 95-109