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Journal Articles

Numerical simulation of annular dispersed flow in simplified subchannel of light water cooled fast reactor RBWR

Yoshida, Hiroyuki; Horiguchi, Naoki; Ono, Ayako; Furuichi, Hajime*; Katono, Kenichi*

Proceedings of 29th International Conference on Nuclear Engineering (ICONE 29) (Internet), 7 Pages, 2022/08

Journal Articles

Experimental investigation of void fraction characteristics for downward steam-water two-phase flow in a large diameter vertical pipe

Katono, Kenichi*; Tamai, Hidesada*; Nagayoshi, Takuji*; Ito, Takashi*; Takase, Kazuyuki

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 8 Pages, 2012/12

no abstracts in English

Journal Articles

Measurement of droplet quality of carryover from free surface using throttling calorimeter

Tamai, Hidesada; Nagayoshi, Takuji; Katono, Kenichi; Ito, Takashi; Takase, Kazuyuki

Proceedings of 7th International Conference on Multiphase Flow 2010 (ICMF 2010) (CD-ROM), 7 Pages, 2010/05

For the design the natural-circulation type BWR that utilizes the FSS concept, the development of a predictive model for the droplets entrained with the steam (carryover) from the free surface is indispensable. In this paper, the droplet quality was measured with a throttling calorimeter that could measure the droplet quality based on the isenthalpic process between wet and superheated steam through the throttle. The measurements were carried out under the conditions of a pressure of 1.5-2.5 MPa. The temperature of the superheated steam after passing through the throttle was confirmed to be strongly related to the quality of the wet steam. A modified model based on the measurements proved to be capable of predicting the droplet quality within the range of the database. Evaluating the droplet quality under BWR conditions validated the feasibility of the design of the natural-circulation type BWR that utilizes the FSS concept.

Journal Articles

Measurement of droplet quality by throttling calorimeter

Tamai, Hidesada; Nagayoshi, Takuji; Katono, Kenichi; Ito, Takashi; Takase, Kazuyuki

Nihon Konsoryu Gakkai Nenkai Koenkai 2009 Koen Rombunshu, P. 2, 2009/08

The characteristics of carryover from free-surface in a natural-circulation BWR are an important subject to be resolved for economic and safe design of the reactor. In this study, droplet quality of the carryover in a test section with 0.12 m in diameter was measured using throttling calorimeter with pressure ranging from 1.5-2.5 MPa. The measured droplet quality increases with decrease in distance from free-surface and with increase in vapor volumetric flux, and these trends are similar to those of previous data.

Oral presentation

Oral presentation

Development of design technology on carryover from free-surface in the upper plenum of natural-circulation type BWRs, 2; Measurement of void fraction under free-surface

Nagayoshi, Takuji*; Tamai, Hidesada; Katono, Kenichi*; Nakagawa, Masaki*; Onuki, Akira

no journal, , 

no abstracts in English

Oral presentation

Development of design technology on carryover from free-surface in the upper plenum of natural-circulation type BWRs, 3; Measurement of droplet diameter/velocity distributions

Tamai, Hidesada; Nagayoshi, Takuji*; Katono, Kenichi*; Nakagawa, Masaki*; Onuki, Akira

no journal, , 

no abstracts in English

Oral presentation

Development of design technology on carryover from free-surface in the upper plenum of natural-circulation type BWRs, 5; Measurement of droplet quality based on isenthalpic change

Tamai, Hidesada; Nagayoshi, Takuji; Katono, Kenichi; Ito, Takashi; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Development of design technology on carryover from free-surface in the upper plenum of natural-circulation type BWRs, 6; Evaluation of reactor based on measurements

Tamai, Hidesada; Nagayoshi, Takuji; Katono, Kenichi; Ito, Takashi; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Thermal-hydraulic tests for downward vapor-water two-phase flow in large diameter pipe, 1; Measurements of cross-sectional average void fraction using electrical type sensor

Tamai, Hidesada; Nagayoshi, Takuji; Katono, Kenichi; Ito, Takashi; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Thermal-hydraulic tests for downward vapor-water two-phase flow in large diameter pipe, 2; Measurement of void fraction distribution by wire-mesh sensor

Katono, Kenichi; Nagayoshi, Takuji; Tamai, Hidesada; Takase, Kazuyuki; Ito, Takashi

no journal, , 

no abstracts in English

Oral presentation

Calculation of void fraction in downcomer of natural-circulation type BWR

Tamai, Hidesada; Nagayoshi, Takuji; Katono, Kenichi; Ito, Takashi; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Two-phase flow measurement techniques for BWR thermal hydraulic conditions, 3; Steam-water tests of ultrasonic liquid film sensor rod

Aoyama, Goro*; Nagayoshi, Takuji*; Katono, Kenichi*; Baba, Atsushi*; Tamai, Hidesada; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Development of light water cooled fast reactor, 4; Numerical simulation of two-phase flow in simplified subchannel

Yoshida, Hiroyuki; Nagatake, Taku; Ono, Ayako; Narushima, Yuki*; Katono, Kenichi*

no journal, , 

no abstracts in English

Oral presentation

Numerical simulation of droplet entrainment and deposition phenomena in annular dispersed flow

Horiguchi, Naoki; Yoshida, Hiroyuki; Narushima, Yuki*; Katono, Kenichi*

no journal, , 

Droplet entrainment and deposition in annular dispersed flow are important phenomena to predict dryout phenomena. Many correlation equations have been proposed to determine the coefficients of entrainment and deposition, but the clarification of entrainment and deposition phenomena is an issue because of the complexity of them and the difficulty of experiments. Detailed numerical simulation is useful for it but requires validation using the correlation equations. In this presentation, we explain the results of the detailed numerical simulation of droplet entrainment and deposition phenomena in annular dispersed flow using TPFIT developed by JAEA and the comparison of the coefficients quantified from the numerical simulation data with the ones using the correlation equations.

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