1988
DOI: 10.13182/nt88-a16054
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Diagnostic Techniques of a Small-Break Loss-of-Coolant Accident at a Pressurized Water Reactor Plant

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Cited by 13 publications
(3 citation statements)
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“…This program includes a two-fluid pressurizer model, a @ PRISM @ includes neutron kinetics, heat transfer from fuel to coolant, a multiple-loop primary coolant system, a pressurizer, and a steam generator. In Japan, a real-time, accidenttracking PWR simulation program has been developed to investigate small break loss-ofcoolant accidents [73]. Cabral developed a three-dimensional, thermal-hydraulic simulation model for a reactor core [59].…”
Section: • 71 S_tement Of Problemmentioning
confidence: 99%
“…This program includes a two-fluid pressurizer model, a @ PRISM @ includes neutron kinetics, heat transfer from fuel to coolant, a multiple-loop primary coolant system, a pressurizer, and a steam generator. In Japan, a real-time, accidenttracking PWR simulation program has been developed to investigate small break loss-ofcoolant accidents [73]. Cabral developed a three-dimensional, thermal-hydraulic simulation model for a reactor core [59].…”
Section: • 71 S_tement Of Problemmentioning
confidence: 99%
“…In the past, there was a model-based approach to diagnosing accidents in nuclear power plants to support operators [1]. Nowadays, the operators' knowledge (database) can be collected using the information obtained from a range of measured data through improvement in the data processing techniques and computing power.…”
Section: Introductionmentioning
confidence: 99%
“…PRISM @ includes neutron kinetics, heat transfer from fuel to coolant, a multiple-loop primary coolant system, a pressurizer, and a steam generator. In Japan, a real-time, accidenttracking PWR simulation program has been developed to investigate small break loss-ofcoolant accidents [73]. Cabral developed a three-dimensional, thermal-hydraulic simulation model for a reactor core [59].…”
mentioning
confidence: 99%