Zobrazeno 1 - 10
of 106
pro vyhledávání: '"Masanori NAITOH"'
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00450-19-00450 (2020)
In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Not only the SFP but also upper spaces of the SFP, walls of the reactor building, and the blowout panel were included. Air oxidation models obtained
Externí odkaz:
https://doaj.org/article/e952e62ca66a4f80b94d238772768d5d
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2016 (2016)
Externí odkaz:
https://doaj.org/article/923fb34f39fa4794acd09496b63c4765
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 81, Iss 831, Pp 15-00303-15-00303 (2015)
Measurement and numerical simulation of the interfacial area concentration and the void fraction were carried out to develop transport equation of interfacial area concentration to fulfill the requirements of an improved prediction accuracy of gas-li
Externí odkaz:
https://doaj.org/article/f9d48ecda80d4ee59aecd2f80e1e4c73
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00450-19-00450 (2020)
In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Not only the SFP but also upper spaces of the SFP, walls of the reactor building, and the blowout panel were included. Air oxidation models obtained
Publikováno v:
SSRN Electronic Journal.
Autor:
Masanori Naitoh, Hiroshige Kikura, Shunsuke Uchida, Masayoshi Kojima, Hidetoshi Okada, Derek H. Liste
Publikováno v:
Nuclear Engineering and Design. 337:84-95
Improvement of plant reliability based on reliability-centered-maintenance (RCM) is going to be undertaken in nuclear power plants (NPPs). RCM is supported by three types of maintenances: risk-based maintenance (RBM); time-based maintenance (TBM); an
Publikováno v:
Annals of Nuclear Energy. 118:212-219
Melt behavior of a BWR in-core monitor (ICM) guide tube, which penetrates a RPV bottom wall, under a severe accident condition was tested using a corium with a mixture of UO 2 , ZrO 2 and Zr. There are several BWR-ICMs; two of them are a short range
Publikováno v:
Nuclear Engineering and Design. 380:111303
Multi-term fission product (FP) analysis procedures were developed to determine FP distribution all over the Fukushima Daiichi nuclear power plant (F1) not only for analyzing accident propagation but also for planning its decommissioning projects. Th
Autor:
Shunsuke Uchida, Masahiko Ohsaka, Marco Pellegrini, Masanori Naitoh, Hidetoshi Karasawa, Chiaki Kino
Publikováno v:
Nuclear Engineering and Design. 380:111256
The safe completion of the Fukushima Daiichi Nuclear Power Plant decommissioning projects requires that the long-term distributions of fission products (FPs) as well as fuel debris for the entire plant be understood. The fuel debris is going to be re
Publikováno v:
Corrosion Engineering, Science and Technology. 52:587-595
A model to evaluate the electrochemical corrosion potential (ECP) and corrosion rate of stainless steel in neutral water was developed by coupling a static electrochemical analysis and a dynamic oxide layer growth analysis. ECP is much affected not o