Safety evaluation of nuclear power plant based on multiscale analyses


  • T Watanabe



A loss-of-coolant accident of nuclear power plant is simulated using the system analysis code. The analytical condition is based on the international standard problem 26 conducted with the integral effect test facility. The experimental analysis is also performed, and the result of plant analysis is compared with the experiment and the experimental analysis. The discharge coefficient of critical flow model is determined so as to obtain the agreement of reactor pressure between the experiment and the experimental analysis, and is used for the plant analysis. The thermal-hydraulic phenomena in the experiment such as core heat up are simulated well by the two analyses, while some problems in the experiment for simulating plant accidents are made clear. Parametric sensitivity analyses of plant accidents are performed as an example of reliable safety evaluation using the validated plant model.


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How to Cite

Watanabe, T. (2021) “Safety evaluation of nuclear power plant based on multiscale analyses”, The International Journal of Multiphysics, 15(2), pp. 169-184. doi: 10.21152/1750-9548.15.2.169.




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