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Journal Articles

Trends of fast reactor cycle technology development in the world, 2; Current status and prospects of sodium-cooled fast reactor cycle technology development in each country

Mishima, Kaichiro*; Saito, Masaki*; Nagata, Takashi*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 52(9), p.536 - 552, 2010/09

The 1st of this series that was entitled, "Accelerating Fast Reactor Development: Start of Operation of Commercial Reactors in 2020" introduced mainly the activated development plan and in the major countries. This article introduces the development of the sodium-cooled fast reactor and related fuel cycle that each country is devoting one's energies to development, maily following the presentation in International Conference (FR09) held by organized by IAEA in December 2009, including the situation before and behind the conference. Especially, the development in Russia, India, China, USA, Republic of Korea, France and Japan.

Journal Articles

Shape measurement of bubble in a liquid metal

Saito, Yasushi*; Shen, X.*; Mishima, Kaichiro*; Matsubayashi, Masahito

Nuclear Instruments and Methods in Physics Research A, 605(1-2), p.192 - 196, 2009/06

 Times Cited Count:9 Percentile:56.98(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Methodology of local instantaneous interfacial velocity measurement in multi-dimensional two-phase flow

Shen, X.*; Mishima, Kaichiro*; Nakamura, Hideo

Proceedings of 14th International Conference on Nuclear Engineering (ICONE-14) (CD-ROM), 8 Pages, 2006/07

Since the transport of momentum, heat and mass tightly links with local interfacial characteristics it is essential to know the local interfacial parameters in various two-phase flows. The interfacial velocity plays a determinant role in determining the other interfacial parameters such as the interfacial area concentration and so on. It is accordingly one of the most important parameters in analyzing two-phase flow. However, it also is one of the most difficult parameters to measure up to now. Based on the application of the interfacial measurement theorem to several four-sensor probes, the present study established a theoretical foundation of the measurement method for the local instantaneous interfacial velocity in multi-dimensional two-phase flow by using three independent four-sensor probes. Since we can find three independent four-sensor probes in a multi-sensor probe, which has more than four sensors, by sharing the sensors of the first four-sensor probe with the sensors of the others, a five- or six-sensor probe including at least one set of three four-sensor combinations was recommended to measure the local instantaneous interfacial velocity, interfacial area concentration and so on in multi-dimensional two-phase flow. A six-sensor probe was developed and employed in the practical measurement in an air-water multi-dimensional two-phase flow in a pool. The six-sensor probe measurements were checked against the gas flow rate measurement using a rotameter and a manometer. The comparing results were very satisfactory.

Journal Articles

An Improved fast neutron radiography quantitative measurement method

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*; Yoshii, Koji*; Okamoto, Koji*

Nuclear Instruments and Methods in Physics Research A, 533(3), p.481 - 490, 2004/11

 Times Cited Count:3 Percentile:25.71(Instruments & Instrumentation)

The validity of a fast neutron radiography quantification method, the $$Sigma$$-scaling method, which was originally proposed for thermal neutron radiography was examined with Monte Carlo calculations and experiments conducted at the YAYOI fast neutron source reactor. Water and copper were selected as comparative samples for a thermal neutron radiography case and a dense object, respectively. Although different characteristics on effective macroscopic cross-sections were implied by the simulation, the $$Sigma$$-scaled experimental results with the fission neutron spectrum cross-sections were well fitted to the measurements for both the water and copper samples. This indicates that the $$Sigma$$-scaling method could be successfully adopted for quantitative measurements in fast neutron radiography.

Journal Articles

Development of a fast neutron radiography converter using wavelength-shifting fibers

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*; Yoshii, Koji*; Okamoto, Koji*

Nuclear Instruments and Methods in Physics Research A, 510(3), p.325 - 333, 2003/09

 Times Cited Count:9 Percentile:55.15(Instruments & Instrumentation)

A fluorescent converter for fast neutron radiography (FNR) comprising a scintillator and hydrogen-rich resin has been developed and applied to electronic imaging. The rate of the reaction between fast neutrons and the converter is increased by thickening the converter, but its opaqueness attenuates emitted light photons before they reach its surface. To improve the luminosity of a fluorescent converter for FNR, a novel type of converter was designed in which wavelength-shifting fibers were adopted to transport radiated light to the observation end face. The performance of the converter was compared with that of a polypropylene-based fluorescent converter in an experiment conducted at the fast-neutron-source reactor YAYOI in the University of Tokyo.

JAEA Reports

Super safe small reactor RAPID-L conceptual design and R&D, JAERI's nuclear research promotion program, H11-002 (Contract research)

Kobe, Mitsuru*; Tsunoda, Hirokazu*; Mishima, Kaichiro*; Kawasaki, Akira*; Iwamura, Takamichi

JAERI-Tech 2003-016, 68 Pages, 2003/03

JAERI-Tech-2003-016.pdf:4.37MB

The 200 kWe uranium nitride fueled lithium cooled fast reactor "RAPID-L" combined with thermoelectric power conversion system that can be operated unmanned without refueling for up to ten years has been demonstrated. The RAPID refueling concept enables quick and simplified refueling, and achieves plant design lifetime over 20 years. A significant advantage of the RAPID-L design, which does not require the use of control rods - is the introduction of the innovative reactivity control systems: lithium expansion module (LEM), lithium injection module (LIM) and lithium release module (LRM). LEM is the most promisiong candidate for improving inherent reactivity feedback. LEMs could realize burnup compensation. LIMs assure sufficient negative reactivity feedback in unprotected transients. LRMs enable an automated reactor startup by detecting the hot standby temperature of the primary coolant. All these systems use $$^{6}$$Li as liquid poison and are actuated by highly reliable physical properties (volume expansion of $$^{6}$$Li for LEM, and freeze seal melting for LIM and LRM).

Journal Articles

Study on point of net vapor generation by neutron radiography in subcooled boiling flow along narrow rectangular channels with short heated length

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

International Journal of Heat and Mass Transfer, 46(7), p.1171 - 1181, 2003/03

 Times Cited Count:9 Percentile:40.01(Thermodynamics)

no abstracts in English

Journal Articles

Super safe fast reactor RAPID with full automatic operation; Application to lunar base and distributed electric power plant on earth

Kobe, Mitsuru*; Tsunoda, Hirokazu*; Mishima, Kaichiro*; Kawasaki, Akira*; Iwamura, Takamichi

Genshiryoku eye, 48(1), p.23 - 28, 2002/01

no abstracts in English

Journal Articles

Void fraction measurement in subcooled-boiling flow using high-frame-rate neutron radiography

Kureta, Masatoshi; Akimoto, Hajime; Hibiki, Takashi*; Mishima, Kaichiro*

Nuclear Technology, 136(2), p.241 - 254, 2001/11

 Times Cited Count:10 Percentile:60.79(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of boiling flow by high-frame-rate neutron radiography, 2; Point of net vapor generation of flow-boiling in rectangular channels with short heated length

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

Nihon Kikai Gakkai Rombunshu, B, 67(661), p.2295 - 2303, 2001/09

no abstracts in English

Journal Articles

Preliminary examination of the applicability of imaging plates to fast neutron radiography

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*; Yoshii, Koji*; Okamoto, Koji*

Nuclear Instruments and Methods in Physics Research A, 463(1-2), p.324 - 330, 2001/05

 Times Cited Count:16 Percentile:74.78(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Fundamental study on interfacial area transport model, 1 (Contract research)

Mishima, Kaichiro*; Nakamura, Hideo

JAERI-Review 2001-012, 51 Pages, 2001/03

JAERI-Review-2001-012.pdf:2.26MB

no abstracts in English

Journal Articles

Measurement of boiling flow by high-frame-rate neutron radiography, 1; Error estimation and void fraction measurement

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

Nihon Kikai Gakkai Rombunshu, B, 67(653), p.179 - 188, 2001/01

no abstracts in English

Journal Articles

Present status on the development of a high-frame-rate neutron radiography system in JRR-3M

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*

Nondestructive Testing and Evaluation, 16(2-6), p.267 - 275, 2001/01

no abstracts in English

Journal Articles

Design and characteristics of the JRR-3M thermal neutron radiography facility and its imaging systems

Matsubayashi, Masahito; Kobayashi, Hisao*; Hibiki, Takashi*; Mishima, Kaichiro*

Nuclear Technology, 132(2), p.309 - 324, 2000/11

 Times Cited Count:24 Percentile:82.34(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Fundamental Research of Two-Phase Flows with High Liquid/Gas Density Ratios

Mishima, Kaichiro*; Hibiki, Takashi*; Saito, Yasushi*; Tobita, Yoshiharu; Konishi, Kensuke; Suzuki, Toru

JNC TY9400 2000-018, 72 Pages, 2000/07

JNC-TY9400-2000-018.pdf:3.92MB

no abstracts in English

Journal Articles

Development of fast neutron radiography imaging technique using imaging plate

Matsubayashi, Masahito; Yoshii, Koji*; Hibiki, Takashi*; Mishima, Kaichiro*

Kashika Joho Gakkai-Shi, 20(Suppl.1), p.325 - 328, 2000/07

no abstracts in English

Journal Articles

Visualization and measurements of liquid phase velocity and void fraction of gas-liquid metal two-phase flow by using neutron radiography

Saito, Yasushi*; Hibiki, Takashi*; Mishima, Kaichiro*; Tobita, Y.*; Suzuki, Toru*; Matsubayashi, Masahito

Proceedings of 9th International Symposium on Flow Visualization, p.391_1 - 391_10, 2000/00

no abstracts in English

Journal Articles

Dynamic neutron radiography; New method of void fraction measurement in subcooled boiling

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

Proceedings of International Workshop on Current Status and Future Directions in Boiling Heat Transfer and Two-Phase Flow, p.103 - 111, 2000/00

no abstracts in English

40 (Records 1-20 displayed on this page)