Development of capacitance void fraction measurement method for BWR test

Watanabe, Hironori; Tamai, Hidesada; Sato, Takashi; Shibata, Mitsuhiko; Mitsutake, Toru*

Flow Measurement, p.95 - 106, 2012/03

https://doi.org/10.5772/39181

In Boiling Water Reactor (BWR), reactor power, fuel conversion ratio and reactor cooling capacity changes by the void fraction in the core. We have developed a capacitance method (C method) to measure the void fraction under the condition of high temperature and high pressure of 7MPa, simulating reactor. This C method is based on the principle that the capacitance in the two-phase flow is a function of void fraction. Using this method, we can measure void fractions in real time, at all region of void fractions, and with a small error of measurement, which was not realized by usual techniques up to now.

Development of electro-void fraction meters for mini-channel

Watanabe, Hironori; Mitsutake, Toru*; Kakizaki, Sadayuki*; Takase, Kazuyuki

Nihon Kikai Gakkai Rombunshu, B, 75(751), p.155 - 157, 2009/03

Capacitance type electro-void fraction meters with various shapes of electrodes were developed for two-phase flow measurement in tubes of 1mm in the smallest diameter. Ring and wire- type electrodes were applied to measure void fraction. The principle of the meter is that the electrical capacitance of a gas-liquid two-phase flow changes with void fraction. A high-frequency power supply enables to measure the low electrical capacitance of the water including pure water. It was confirmed by the air-water two-phase flow experiments that void fraction can be obtained in real time way every 50 millisecond. Void fraction in the experiment ranged from 0 to higher than 0.9. The void fraction was correlated with the electric capacitance by a linear function for the ring-electrode and hyperbolic function for the opposite wires-electrode under the atmospheric condition.

Data report of tight-lattice rod bundle thermal-hydraulic tests, 3; Rod-bowing effect test using 37-rod bundle simulated water-cooled breeder reactor (Contract research)

Tamai, Hidesada; Kureta, Masatoshi; Liu, W.; Sato, Takashi; Nakatsuka, Toru; Watanabe, Hironori; Onuki, Akira; Akimoto, Hajime

JAEA-Data/Code 2007-011, 126 Pages, 2007/03

JAEA-Data-Code-2007-011.pdf:43.43MB

Japan Atomic Energy Agency has been performing tight-lattice rod bundle thermal-hydraulic tests to realize essential technologies for the technological and engineering feasibility of super high burn-up water-cooled breeder reactor featured by a high breeding ratio and super high burn-up by reducing the core water volume in water-cooled reactor. The tests were performing to make clear the fundamental subjects related to the boiling transition (BT) (Subjects: BT criteria under a highly tight-lattice rod bundle, effects of gap-width between rods and of rod-bowing) using 37-rod bundles (Base case test section (1.3 mm gap-width), Two parameter effect test sections (Gap-width effect one (1.0 mm) and Rod-bowing one)). In the present report, we summarize the test results from the rod-bowing effect test section. The thermal-hydraulic characteristics were obtained for the critical power under the steady-state and transient conditions, the pressure drop and the wall heat transfer within a wide range of pressure, flow rate, etc. including normal operational conditions of the designed reactor. Then the rod-bowing effects were also investigated based on the comparison between the results using the base case test section and the rod-bowing effect one.

Data Report of a tight-lattice rod bundle thermal-hydraulic tests, 1; Base case test using 37-rod bundle simulated water-cooled breeder reactor (Contract research)

Kureta, Masatoshi; Tamai, Hidesada; Liu, W.; Sato, Takashi; Watanabe, Hironori; Onuki, Akira; Akimoto, Hajime

JAEA-Data/Code 2006-007, 90 Pages, 2006/03

JAEA-Data-Code-2006-007.pdf:14.83MB

Japan Atomic Energy Agency has been performing tight-lattice rod bundle thermal-hydraulic tests as one of essential technologies for the technological and engineering feasibility of super high burn-up water-cooled breeder reactor which aims to achieve a high breeding ratio and super high burn-up by innovative performance-up of water-cooled reactor. The tests are performing to make clear the fundamental subjects related to the boiling transition(BT)(Subjects:BT criteria under a highly tight-lattice rod bundle, effects of gap-width between rods and of rod-bowing) using 37-rod bundles (Base case test section (1.3mm gap-width), Two parameter effect test sections (Gap-width effect one (1.0mm) and Rod-bowing one)). In the present report, we summarize the test results from the base case test section. The thermal-hydraulic characteristics using the large scale test section were obtained for the critical power, the pressure drop and the wall heat transfer under a wide range of pressure, flow rate, etc. including normal operational conditions of the designed reactor. Effects of local peaking factor on the critical power were also obtained.

CHF experiments of tight pitch lattice rod bundles under PWR pressure condition for development of reduced moderation water reactor

Araya, Fumimasa; Nakatsuka, Toru; Yoritsune, Tsutomu; Kureta, Masatoshi; Yoshida, Hiroyuki; Ishikawa, Nobuyuki; Sato, Takashi; Watanabe, Hironori; Okubo, Tsutomu; Iwamura, Takamichi; et al.

JAERI-Research 2002-018, 37 Pages, 2002/10

JAERI-Research-2002-018.pdf:2.62MB

no abstracts in English

Data report of BWR post-CHF tests; Transient core thermal-hydraulic program (Contract research)

Iguchi, Tadashi; Ito, Hideo; Kiuchi, Toshio; Watanabe, Hironori; Kimura, Mamoru*; Anoda, Yoshinari

JAERI-Data/Code 2001-013, 502 Pages, 2001/03

JAERI-Data-Code-2001-013.pdf:32.38MB

no abstracts in English

Experimental study on thermal-hydraulic behaviors of a pressure balanced coolant injection system for a passive safety light water reactor JPSR

Sato, Takashi; Watanabe, Hironori; Araya, Fumimasa; Nakajima, Katsutoshi; Iwamura, Takamichi; Murao, Yoshio

JAERI-Research 98-006, 77 Pages, 1998/02

JAERI-Research-98-006.pdf:3.27MB

no abstracts in English

A Concept of a passive safety light water reactor system requiring reduced maintenance efforts

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Watanabe, Hironori

Transactions of the American Nuclear Society, 69, p.539 - 540, 1993/00

no abstracts in English

Safety demonstration tests of postulated solvent fire accidents in extraction process of a fuel reprocessing plant, Part III

Takada, Junichi; Koike, Tadao; Tsukamoto, Michio; Nishio, Gunji; Kitani, Susumu*; Uno, Seiichiro; ; Watanabe, Hironori; Hashimoto, Kazuichiro

JAERI-M 92-048, 332 Pages, 1992/03

JAERI-M-92-048.pdf:5.41MB

no abstracts in English

Evaluation of mechanistic DNB models using HCLWR CHF data

Iwamura, Takamichi; Watanabe, Hironori; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

JAERI-M 92-033, 66 Pages, 1992/03

JAERI-M-92-033.pdf:1.37MB

no abstracts in English