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A platform for research: civil engineering, architecture and urbanism
Probability analysis of reinforced concrete structure failure of nuclear power plants due to loss of coolant accident
This paper describes the probabilty analysis of reinforced concrete containment structure of NPP with the reactor VVER V-230 under high internal overpressure. The summary of calculation models and calculation methods for the probability analysis of the structural integrity in the case of the loss of coolant accident (LOCA) is showed. The probabilistic structural analysis (PSA) level 2 aims at an assessment of the probability of the concrete structure failure under excessive overpressure. In the non-linear analysis of the concrete structures a layered approximation of the shell elements with various material properties have been included. The uncertainties of longtime temperature and dead loads, material properties (concrete cracking and crushing, reinforcement, and liner) and model uncertainties were taken into account in the 106 direct MONTE CARLO simulations. The results of the probability analysis of the containment failure under excessive overpressure show that in the case of the LOCA accident at overpressure of 122,7 kPa the probability is smaller than the required 10-4 for design resistance. ; Obsahuje seznam literatury
Probability analysis of reinforced concrete structure failure of nuclear power plants due to loss of coolant accident
This paper describes the probabilty analysis of reinforced concrete containment structure of NPP with the reactor VVER V-230 under high internal overpressure. The summary of calculation models and calculation methods for the probability analysis of the structural integrity in the case of the loss of coolant accident (LOCA) is showed. The probabilistic structural analysis (PSA) level 2 aims at an assessment of the probability of the concrete structure failure under excessive overpressure. In the non-linear analysis of the concrete structures a layered approximation of the shell elements with various material properties have been included. The uncertainties of longtime temperature and dead loads, material properties (concrete cracking and crushing, reinforcement, and liner) and model uncertainties were taken into account in the 106 direct MONTE CARLO simulations. The results of the probability analysis of the containment failure under excessive overpressure show that in the case of the LOCA accident at overpressure of 122,7 kPa the probability is smaller than the required 10-4 for design resistance. ; Obsahuje seznam literatury
Probability analysis of reinforced concrete structure failure of nuclear power plants due to loss of coolant accident
Králik, Juraj (author)
Miscellaneous
Electronic Resource
English
DDC:
690
Loss-of-Coolant Accident Investigations
NTIS | 1968
Pump Model for Loss-of-Coolant Accident Analysis
| NTIS | 1972
| British Library Conference Proceedings | 2014