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Kureta, Masatoshi
Ryutai Keisokuho; Kaitei-Han, p.367 - 371, 2022/04
The Japan Society of Mechanical Engineers publishes a revised version of the technical document summarizing fluid measurement techniques. This article is part of the application section, and the main content is an introduction of application examples using advanced thermal-fluid measurement technology that is progressing remarkably. In the chapter "Void Fraction Distribution Measurement", the technology for visualizing and measuring the void fraction distribution with neutron beams for the two-phase flow of gas-liquid flowing inside the instrument is summarized. In the first half, the definition of void fraction, measurement by neutron transmission method, and basic principles of CT imaging technology were explained. In the second half, visualization and measurement results were shown in the order of two-dimensional and two-dimensional time changes of various multiphase flows, and three-dimensional and three-dimensional time changes.
Esaka, Fumitaka; Sakurai, Satoshi
Kaku Busshitsu Kanri Senta Nyusu, 33(11), p.9 - 12, 2004/11
no abstracts in English
Usuda, Shigekazu
Kaku Busshitsu Kanri Senta Nyusu, 32(10), p.5 - 6, 2003/10
no abstracts in English
Kureta, Masatoshi
KEK Proceedings 2001-9, p.35 - 39, 2001/04
no abstracts in English
Odo, Toshihiro;
PNC TN9420 92-005, 83 Pages, 1992/04
This report introduces the nuclear instrumentation system and major R&D (research and development) activities using radiation measurement techniques in Experimental Fast Reactor "JOYO". In the introduction of the nuclear instrumentation system, following items are described; (1)system function (2)roles as a reactor plant equipment (3)specifications and charactelistics of neutron detectors, (4)construction and layout of the system. For reactor dosimetry at various irradiation tests and surveillance tests, multi-foil method employed in "JOYO", neutron fluence evaluation using activation foils and HAFM (Helium Accumulation Fluence Monitor) under development are described briefly. The failed fuel detection system and some experimental equipments using radiation measurement techniques are also introduced here with main results obtained by a series of fuel failure simulation experiments. In addition, following R&Ds are picked up as some examples based on radiation measurement technology; (1)burn-up measurement of spent fuel subassembly (2)measurement and evaluation of radiation source distributions (radioactive corrosion products)
Genshiro Zairyo Dai-122 Iinkai Showa-63-Nendo Dai-1-Kai Iinkai Shiryo, p.8 - 15, 1988/00
no abstracts in English
;
Genshiryoku Kogyo, 21(1), p.44 - 48, 1975/01
no abstracts in English
Nakayama, Jiro; Sumi, Hirotaka; Kuboki, Michikatsu; Kodaka, Akira; Fujiwara, Koji
no journal, ,
no abstracts in English
Ono, Ayako; Yamaguchi, Manabu*; Sakashita, Hiroto*; Uesawa, Shinichiro; Shibata, Mitsuhiko; Yoshida, Hiroyuki
no journal, ,
The establishment of the evaluation method of the critical heat flux for light water reactors is needed. However, the boiling phenomena under high pressure remain to be clarified. The measurement system based on detecting the electric capacitance has been developed, which detects the liquid-vapor behavior vicinity of the heating surface in order to clarify the mechanism of the critical heat flux under the higher pressure region. In this study, the detail of the measurement system and the result to confirm the validity of the measurement system are reported.
Torii, Tatsuo; Sanada, Yukihisa
no journal, ,
no abstracts in English
Ono, Ayako; Okamoto, Kaoru*; Makino, Yasushi*; Hosokawa, Shigeo*; Yoshida, Hiroyuki
no journal, ,
JAEA has been developing an advanced neutronic/thermal-hydraulics coupling simulation system. In the system, the detailed thermal-hydraulics codes JUPITER and TPFIT, which are based on an interface-capturing method, will be adopted to simulate thermal-hydraulics in a fuel bundle. The experimental data and findings relating to the two-phase flow in a fuel bundle are needed to validate JUPITER and TPFIT. In this study, we propose a new measurement method to measure the bubbly flow in a narrow channel, such as a subchannel, by combining laser-doppler velocimetry and photodiodes. The proposed measurement method is cross-checked by a conductance probe and is confirmed for its validity.
Sato, Yuki
no journal, ,
At the Waste Management Conference 2024, the development of radiation measurement technology conducted by the CLADS Advanced Radiation Measurement and Analysis Research Group will be presented, with a focus on those that have been demonstrated at the Fukushima Daiichi Nuclear Power Station.
Ono, Ayako; Okamoto, Kaoru*; Makino, Yasushi*; Hosokawa, Shigeo*; Yoshida, Hiroyuki
no journal, ,
JAEA has been developing an advanced neutronic/thermal-hydraulics coupling simulation system. In the coupling code, the detailed thermal-hydraulics codes based on an interface-capturing method (JUPITER or TPFIT) will be adopted to simulate thermal-hydraulics in a fuel bundle. The experimental data and findings relating to the two-phase flow in a fuel bundle are needed to validate the JUPITER/TPFIT codes. In the previous study, we proposed a new measurement method to measure the bubbly flow in a narrow channel, such as a subchannel, by combining laser-doppler velocimetry and photodiodes. In this study, we evaluate the uncertainty in the new measurement method arising from the signal processing and the method of the determination for bubble signals, using the newly developed LDV optical path simulator.
Terashima, Kenichi; Matsumura, Taichi; Sakamoto, Masahiro; Kaburagi, Masaaki; Shiba, Tomooki; Sugizaki, Saki*; Okumura, Keisuke
no journal, ,
no abstracts in English
Abe, Yuta; Ara, Kuniaki
no journal, ,
no abstracts in English
Toh, Yosuke
no journal, ,
no abstracts in English
Kaburagi, Masaaki; Shiba, Tomooki; Matsumura, Taichi; Sakamoto, Masahiro; Terashima, Kenichi; Sugizaki, Saki*; Okumura, Keisuke
no journal, ,
no abstracts in English
Yoshida, Hiroyuki; Horiguchi, Naoki; Ono, Ayako
no journal, ,
Since innovative reactors' flow conditions and geometries may differ from those of conventional reactors, the applicability of the models and correlations used in the design works should be appropriately checked. In the design phase, there is a high possibility that the flow conditions and geometries will be changed. Therefore, applying detailed numerical simulation is expected to achieve efficient design works. In nuclear reactors, two-phase flow will appear in many situations. Confirming the applicability of models and correlations for two-phase flow conditions is essential. The detailed two-phase flow simulation codes must be useful to verify the applicability of two-phase flow models and correlations. However, there is no established methodology to validate detailed two-phase flow simulations properly. We have, therefore, started the research project to develop a method for validating detailed two-phase flow simulation codes. In this project, we have developed two-phase flow measurement technologies to obtain detailed information on the gas-liquid interface and two-phase flow database by using developed measurement technologies and performing detailed two-phase flow simulations for the developed two-phase flow database. We will compare detailed two-phase flow simulation results and the two-phase flow database and discuss the proper methodology with the reactor manufacturer. Finally, we will investigate the validation process of a detailed two-phase flow simulation code. In this presentation, we will show the outline of this project and plans.
Moriguchi, Daisuke*; Ono, Ayako; Okamoto, Kaoru*; Hosokawa, Shigeo*; Fukuzato, Katsuhiko*; Machii, Jun*; Yoshida, Hiroyuki; Nakamura, Kenichi*; Kishibe, Tadaharu*; Morishige, Naoki*; et al.
no journal, ,
The objective of this study is to provide experimental data applied to the validation of detailed two-phase flow simulation codes. To achieve this aim, we propose the developed measurement method for gas-liquid two-phase bubbly flow through the combination of Laser Doppler Velocimetry (LDV) and photodiode technology. This method is capable of simultaneously measuring liquid velocity and local void fraction. The development plan is briefly introduced in the presentation.
