APPLICATION EXAMPLE TO DEMONSTRATE RIPB SEISMIC DESIGN CONCEPTS FOR ADVANCED NUCLEAR POWER REACTORS

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:International Conference on Structural Mechanics in Reactor Technology (26. : 2022 : Berlin; Potsdam) 26th International Conference on Structural Mechanics in Reactor Technology 2022 (SMiRT 26) ; Volume 2 of 5
1. Verfasser: Chokshi, N. (VerfasserIn)
Weitere Verfasser: Dasgupta, B. (VerfasserIn), Ravindra, M. (VerfasserIn), Budnitz, R. (VerfasserIn), Stamatakos, J. (VerfasserIn), Pensado, O. (VerfasserIn)
Pages:26
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2023
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
NUMERICAL SIMULATION OF EXPERIMENTS ON IMPACT INDUCED VIBRATIONS – COMPARISON OF IRIS PHASE 3 AND IMPACT V3 MOCK-UPS WITH RESPECT TO BOUNDARY CONDITIONS 2023 Heckotter, C.
THE APPLICATION OF RISK INFORMED DESIGN AND RISK INFORMED REGULATION TO THE EXTERNAL HAZARDS DESIGN OF NUCLEAR FACILITIES 2023 Ford, P.
COMPUTATIONALLY EFFICIENT ALGORITHMS FOR RISK INFORMED DECISION MAKING IN NUCLEAR PRA 2023 Vaishanav, P.
ESTIMATION OF SEISMIC HAZARD SEVERITY CORRESPONDING TO THE CLIFF EDGE EFFECT 2023 Coman, O.
SEISMIC EVALUATION OF CLIFF EDGE EFFECTS FOR THE ICC FUNCTION AT RINGHALS NPP 2023 Graf, T.
BEST-ESTIMATE WATER HAMMER SIMULATIONS TO AVOID THE CALCULATION OF UNREALISTICALLY HIGH LOADS OR UNPHYSICAL PRESSURE AND FORCE PEAKS 2023 Neuhaus, T.
FATIGUE ASSESSMENT OF GROOVES FOR GASKETS IN REACTOR MAIN FLANGE 2023 Gal, P.
ANALYSIS OF PRESSURIZED THERMAL SHOCKS FOR ECCS NOZZLE OF VVER REACTOR PRESSURE VESSEL 2023 Pistora, V.
CONSIDERATION OF IMPORTANT EFFECTS IN ENVIRONMENTALLY ASSISTED FATIGUE (EAF) OF AUSTENITIC AND FERRITIC STEEL COMPONENTS INCLUDING WELDS AND DEVELOPMENT OF A PRACTICAL FATIGUE ASSESSMENT CONCEPT 2023 Rudolph, J.
CONCRETE DISTRIBUTED STRAIN MEASUREMENTS FEEDBACK ON CIVIL STRUCTURES BASED ON VERCORS MOCKUP – POTENTIAL APPLICATION FOR NEW NPP’S 2023 Galan, M.
LARGE-SCALE CAST-IN-PLACE PRACTICE OF SPECIAL CONCRETE FOR NUCLEAR REACTOR BUILDINGS - ULTRA-HIGHPERFORMANCE CONCRETE WITH A SPECIFIED COMPRESSIVE STRENGTH OF 150 MPA 2023 Qiao, D.
PUNCHING FAILURE OF REINFORCED CONCRETE SLABS SUBJECTED TO HARD MISSILE IMPACT: SIMULATION OF INFLUENCE OF SLAB THICKNESS & SHEAR REINFORCEMENT IN LS-DYNA 2023 Khasraghy, S.
A SYNTHESIS OF THE VTT IMPACT PROJECT PHASES II AND III 2023 Galan, M.
EVALUATION OF SEISMIC CAPACITY OF NUCLEAR INSTALLATION EQUIPMENT BASED ON SEISMIC EXPERIENCE DATA 2023 Altinyollar, A.
VERIFICATION OF THE MASTER CURVE CONCEPT (ASTM E1921) FOR THE WELD OF A GERMAN RPV STEEL AT VARIOUS LOADING RATES 2023 Tlatlik, J.
CLOSED FORM FORMULAE FOR TWO INTERACTING EQUAL PARALLEL THROUGHWALL CRACKS EMBEDDED IN AN INFINITE ELASTIC MEDIUM UNDER NORMAL TENSION 2023 Gilles, P.
INTERNATIONAL LEAK RATE BENCHMARK: PHASE ONE RESULTS OF THE OECD/NEA/CSNI ACTIVITY 2023 Heckmann, K.
CSNI LEAK-BEFORE-BREAK BENCHMARK – SUMMARY OF PHASE I 2023 Tregoning, R.
LEAK BEFORE BREAK DETERMINATION: SENSITIVITY OF ANALYST INPUT PARAMETER CHOICES 2023 Wallace, J.
SEISMIC ANALYSIS OF OVERHEAD CRANE BRIDGES USING FRICTION-BASED SLIDING MODEL 2023 Colomb, J.
Alle Artikel auflisten