Search Results - "NAITOH, Masanori"

Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool (confirmation of fuel temperature calculation function with oxidation reaction in the SAMPSON code) by SUZUKI, Hiroaki, MORITA, Yoshihiro, NAITOH, Masanori, NEMOTO, Yoshiyuki, KAJI, Yoshiyuki

“…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…”
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Evaluation of flow accelerated corrosion by coupled analysis of corrosion and flow dynamics. Relationship of oxide film thickness, hematite/magnetite ratio, ECP and wall thinning rate by Uchida, Shunsuke, Naitoh, Masanori, Okada, Hidetoshi, Uehara, Yasushi, Koshizuka, Seiichi

“…Systematic approaches to evaluate flow accelerated corrosion (FAC) are desired before discussing application of countermeasures for FAC. First, future FAC…”
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Modeling of turbulent transport term of interfacial area concentration in gas–liquid two-phase flow by Kataoka, Isao, Yoshida, Kenji, Naitoh, Masanori, Okada, Hidetoshi, Morii, Tadashi

“…► Transport equation of interfacial area concentration is derived. ► Conservation equation of interfacial velocity is derived. ► Turbulent transport terms of…”
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Advanced PHWR Safety Technology: PHWR Challenging Issues for Safe Operation and Long-Term Sustainability by Song, Jin Ho, Shen, Wei, Griffiths, Malcolm, Rhee, Bo Wook, Song, YongMann, Naitoh, Masanori

“…Jin Ho Song 1 and Wei Shen 2 and Malcolm Griffiths 3 and Bo Wook Rhee 1 and YongMann Song 1 and Masanori Naitoh 4 1, Korea Atomic Energy Research Institute…”
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Prediction of the critical heat flux in annular regime in various vertical channels by Okawa, Tomio, Kotani, Akio, Kataoka, Isao, Naitoh, Masanori

“…The axial variation of film flow rate in annular regime was analyzed to predict the critical heat flux in water saturated flow boiling in various vertical…”
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Conversion factors bridging radiocative fission product distributions in the primary containment vessel of Fukushima daiichi npp and dose rates measured by the containment atmosphere monitoring system by Uchida, Shunsuke, Pellegrini, Marco, Naitoh, Masanori

“…•The multi-term FP behavior analyses were validated with the CAMS dose rate data.•The conversion factors can bridge the measured dose rates and analyzed FP…”
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Experimental study and numerical simulation of interfacial area transport of bubbly flow by Atsushi ISHIKAWA, Masanori NAITOH, Kenji YOSHIDA, Isao KATAOKA

“…Measurement and numerical simulation of the interfacial area concentration and the void fraction were carried out to develop transport equation of interfacial…”
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Analysis on pipe rupture of steam condensing line at Hamaoka-1, (I): Accumulation of non-condensable gas in a pipe by NAITOH, Masanori, KASAHARA, Fumio, MITSUHAKHI, Toshihani, OHSHIMA, Iwan

“…A pipe rupture occurred in the steam condensing line of the residual heat removal system at the Hamaoka Nuclear Power Station Unit-1 on November 7, 2001. The…”
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An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accident by Uchida, Shunsuke, Karasawa, Hidetoshi, Kino, Chiaki, Pellegrini, Marco, Naitoh, Masanori, Ohsaka, Masahiko

“…The safe completion of the Fukushima Daiichi Nuclear Power Plant decommissioning projects requires that the long-term distributions of fission products (FPs)…”
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Effects of oxide layers on zirconium alloy-steam reaction by Uchida, Shunsuke, Naitoh, Masanori, Okada, Hidetoshi, Hanamoto, Yukio

“…In a severe accident of a BWR plant, zirconium alloy of fuel cladding reacts with steam becoming a heat source for core melting and becoming a hydrogen source…”
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Analysis on pipe rupture of steam condensation line at Hamaoka-1, (II) hydrogen combustion and pipe deformation by NAITOH, Masanori, KASAHARA, Fumio, KUBOTA, Ryoko, OHSHIMA, Iwao

“…A pipe rupture occurred in the steam condensing line of the residual heat removal system at the Hamaoka Nuclear Power Station Unit-1 on November 7, 2001. As…”
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Experimental investigation on molten pool representing corium composition at Fukushima Daiichi nuclear power plant by An, Sang Mo, Song, Jin Ho, Kim, Jong-Yun, Kim, HwanYeol, Naitoh, Masanori

“…A configuration of molten core in the Fukushima Daiichi NPP (nuclear power plant) was investigated by a melting and solidification experiment. About 5 kg of a…”
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Improvement of plant reliability based on combination of prediction and inspection of wall thinning due to FAC by Uchida, Shunsuke, Okada, Hidetoshi, Naitoh, Masanori, Kojima, Masayoshi, Kikura, Hiroshige, Liste, Derek H.

“…•The combination of prediction and inspection is one of the key issues to promote risk-based maintenance (RBM).•As an example of RBM, the combination of the…”
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Temperature dependent fission product removal efficiency due to pool scrubbing by Uchida, Shunsuke, Itoh, Ayumi, Naitoh, Masanori, Okada, Hidetoshi, Suzuki, Hiroyuki, Hanamoto, Yukio, Osakabe, Masahiro, Fujikawa, Masahiro

“…•Pool temperature effects on the FP removal were not clearly concluded in the previous publications.•It was confirmed that the removal efficiency decreased…”
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Suppression pool testing at the SIET laboratory: experimental investigation of critical phenomena expected in the Fukushima Daiichi suppression chamber by Pellegrini, Marco, Araneo, Lucio, Ninokata, Hisashi, Ricotti, Marco, Naitoh, Masanori, Achilli, Andrea

“…In the unlikely event of a nuclear power plant long duration station black-out, as in the Fukushima Daiichi (1F) severe accident (SA), it was recognized that…”
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Improvement of plant reliability based on combining of prediction and inspection of crack growth due to intergranular stress corrosion cracking by Uchida, Shunsuke, Chimi, Yasuhiro, Kasahara, Shigeki, Hanawa, Satoshi, Okada, Hidetoshi, Naitoh, Masanori, Kojima, Masayoshi, Kikura, Hiroshige, Lister, Derek H.

“…•The combination of prediction and inspection is one of the key issues to promote risk-based maintenance (RBM).•As an example of RBM, the combination of the…”
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Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project by UJITA, Hiroshi, IKEDA, Takashi, NAITOH, Masanori

“…SAMPSON is the integral code for severe accident analysis in detail with modular structure, developed in the IMPACT project. Each module can run independently…”
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Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool (confirmation of fuel temperature calculation function with oxidation reaction in the SAMPSON code) by SUZUKI, Hiroaki, MORITA, Yoshihiro, NAITOH, Masanori, NEMOTO, Yoshiyuki, KAJI, Yoshiyuki

“…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…”
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Melting test of penetrating tube through BWR-RPV bottom wall by Naitoh, Masanori, Suzuki, Hiroyuki, Pellegrini, Marco, An, Sang Mo, Song, Jin Ho

“…•Melt behavior of a BWR in-core monitor guide tube made of steel was tested.•The test simulated severe accident condition with a mixture corium of UO2 and…”
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Development of Severe Accident Analysis Code SAMPSON in IMPACT Project by UJITA, Hiroshi, SATOH, Nobuhide, NAITOH, Masanori, HIDAKA, Masataka, SHIRAKAWA, Noriyuki, YAMAGISHI, Makoto

“…IMPACT is the name of a program and of specific simulation software, which will perform full-scope and detailed calculations of various phenomena in a nuclear…”
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