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Journal Articles

Characteristics of heat transfer inside tube during sodium-water reaction in FBR steam generator

Kurihara, Akikazu; Ohshima, Hiroyuki; Monde, Masanori*

Heat Transfer-Asian Research, 39(8), p.628 - 633, 2010/12

To predict sodium-water reaction (SWR) of steam generator (SG) in fast breeder reactor with high accuracy, it is very important to understand the characteristics of heat transfer inside the tube in detail during tube failure due to SWR. Test tube was heated rapidly by high frequency current. Time averaged heat flux was estimated by using an inverse solution. It was confirmed that the derived values agreed with measured heat fluxes on the outer surface within 20% accuracy. It was found that the characteristics of heat transfer strongly depend on the flow rate. Heat transfer on the wall changed from nucleate to transient-film boiling during increasing heat flux and returned to nucleate boiling during decreasing the heat flux. The nucleate and film boiling coexisted and the area ratio of these varied with time in the transition boiling region. The adequacy of heat transfer correlations to evaluate overheating was confirmed.

Journal Articles

Characteristics of heat transfer inside tube during sodium-water reaction in FBR steam generator

Kurihara, Akikazu; Ohshima, Hiroyuki; Monde, Masanori*

Nihon Kikai Gakkai Rombunshu, B, 76(763), p.442 - 444, 2010/03

Sodium reacts chemically with water in the case of the unexpected tube failure of a steam generator (SG) in a fast breeder reactor (FBR). It is integral in order to predict the event with high accuracy to understand the characteristics of heat transfer inside a tube in detail during the tube failure (sodium-water reaction). Experiments were performed using purified water under the following conditions; initial pressure of 11.2-13.4 MPa, initial water temperature of 200 $$^{circ}$$C and water mass flux of 45.7-3630 kg/(m$$^{2}$$s). A test tube was heated rapidly by high frequency induction current. The time averaged heat flux was estimated using an inverse solution from the measured temperatures at two points on three different locations along the tube. It was confirmed that the derived values agreed with measured heat fluxes on the outer surface within 20% accuracy. It was found that the characteristics of the heat transfer strongly depended on the flow rate. The heat transfer on the wall changed from nucleate boiling to transient-film boiling during increasing the heat flux and returned to the nucleate boiling during decreasing the heat input. A counterclockwise cycle always appeared in the transition boiling region, where the nucleate and film boiling coexisted and the area ratio of these varied with time. The adequacy of heat transfer correlations to evaluate tube overheating were confirmed.

Journal Articles

Characteristics of heat transfer inside vertical tube in FBR steam generator

Kurihara, Akikazu; Monde, Masanori*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 8(2), p.102 - 109, 2009/06

An experimental study has been carried out to clarify relationship between flow aspect and heat transfer mode during downward flow in a vertical tube of FBR steam generator. The experiment was done using purified water under the following conditions; initial pressure of 11.2-13.4 MPa, initial water temperature of 200 $$^{circ}$$C and water flow rate of 0.021-1.67 kg/s. The tube was heated by high frequency induction current, where the time averaged heat flux can be estimated using an inverse solution from the measured temperatures at two points on three different positions along the tube wall and then is confirmed to agree with the outer surface measured heat flux within 20% accuracy. It is found that the heat transfer characteristics strongly depend on the flow rate. In high mass flow rate, a stable nucleate boiling is formed on a vertical tube wall with clockwise cycle on $$q$$-$$Delta$$$$T$$ diagram for heat flux changes during $$dq/d$$$$Delta$$$$T$$$$>$$0 at any time. In low mass flow rate, boiling on the wall changes from dq/d$$Delta$$$$T$$$$>$$0 to dq/d$$Delta$$$$T$$$$<$$0 during the heating and returns from $$dq/d$$$$Delta$$$$T$$$$<$$0 to $$dq/d$$$$Delta$$$$T$$$$>$$0 during the reduction in heat.

Journal Articles

Experimental investigation of characteristics of impinging jet heat transfer and application to JSNS moderator design

Aso, Tomokazu; Monde, Masanori*; Sato, Hiroshi; Hino, Ryutaro; Tatsumoto, Hideki; Kato, Takashi

Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(3), p.179 - 189, 2006/09

no abstracts in English

Journal Articles

Estimation of JSNS moderator flowing condition based on impinging jet heat transfer

Aso, Tomokazu; Monde, Masanori*; Sato, Hiroshi; Tatsumoto, Hideki; Kato, Takashi; Ikeda, Yujiro

LA-UR-06-3904, Vol.2, p.385 - 394, 2006/06

no abstracts in English

Journal Articles

New-type neutron source with proton accelerator and its application

Hino, Ryutaro; Yokomizo, Hideaki; Yamazaki, Yoshishige; Hasegawa, Kazuo; Suzuki, Hiromitsu; Soyama, Kazuhiko; Hayashi, Makoto*; Haga, Katsuhiro; Kaminaga, Masanori; Sudo, Yukio*; et al.

Nihon Kikai Gakkai-Shi, 107(1032), p.851 - 882, 2004/11

no abstracts in English

Journal Articles

Flow behaviors of impinging jet in cold moderator vessel for spallation neutron source; Flow visualization and preliminary heat transfer experiment

Aso, Tomokazu; Sato, Hiroshi; Kaminaga, Masanori; Hino, Ryutaro; Monde, Masanori*

Kashika Joho Gakkai-Shi, 23(Suppl.2), p.13 - 16, 2003/10

no abstracts in English

Journal Articles

Thermal-hydraulic experiments and analyses of coupled moderator vessel for spallation neutron source

Aso, Tomokazu; Sato, Hiroshi; Kaminaga, Masanori; Hino, Ryutaro; Monde, Masanori*

Nihon Kikai Gakkai Kanto Shibu Ibaraki Koenkai (2003) Koen Rombunshu (No.030-3), p.45 - 46, 2003/09

no abstracts in English

Journal Articles

Thermal-hydraulic design of J-PARC cold moderators

Aso, Tomokazu; Sato, Hiroshi; Kaminaga, Masanori; Hino, Ryutaro; Monde, Masanori*

Proceedings of ICANS-XVI, Volume 2, p.935 - 944, 2003/07

no abstracts in English

Journal Articles

Thermal-hydraulic experiments and analyses for cold moderators

Aso, Tomokazu; Kaminaga, Masanori; Hino, Ryutaro; Monde, Masanori*

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 8 Pages, 2003/04

no abstracts in English

JAEA Reports

Analytical study of narrow channel flow for a spallation target system design

Islam, M. S.*; Terada, Atsuhiko*; Kinoshita, Hidetaka; Hino, Ryutaro; Monde, Masanori*

JAERI-Tech 2001-044, 49 Pages, 2001/07

JAERI-Tech-2001-044.pdf:2.49MB

no abstracts in English

Journal Articles

Experimental study on heat transfer augmentation for high heat flux removal in rib-roughened narrow channels

M.S.Islam*; Hino, Ryutaro; Haga, Katsuhiro; Monde, Masanori*; Sudo, Yukio

Journal of Nuclear Science and Technology, 35(9), p.671 - 678, 1998/09

 Times Cited Count:15 Percentile:75.72(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Experimental study on heat transfer augmentation for high heat flux removal in rib-roughened narrow channels

M.S.Islam*; Hino, Ryutaro; Haga, Katsuhiro; Monde, Masanori*; Sudo, Yukio

JAERI-Tech 97-032, 49 Pages, 1997/07

JAERI-Tech-97-032.pdf:1.53MB

no abstracts in English

JAEA Reports

Heat transfer augmentation for high heat flux removal in rib-roughened narrow channels

M.S.Islam*; Hino, Ryutaro; Haga, Katsuhiro; Monde, Masanori*; Sudo, Yukio

JAERI-Tech 97-008, 46 Pages, 1997/03

JAERI-Tech-97-008.pdf:1.43MB

no abstracts in English

Journal Articles

Current trends of thermal-hydraulic research on severe accident

Nariai, Hideki*; Sugiyama, Kenichiro*; Kataoka, Isao*; Mishima, Kaichiro*; *; Monde, Masanori*; Sugimoto, Jun; ; Hidaka, Akihide; *; et al.

Nihon Genshiryoku Gakkai-Shi, 39(9), p.739 - 752, 1997/00

 Times Cited Count:1 Percentile:13.16(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Simulation test of heat transfer inside tube in case of sodium-water reaction in fbr steam generators

Kurihara, Akikazu; Monde, Masanori*; Ohshima, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Heat transfer characteristics of rapidly heating tube in FBR steam generator

Kurihara, Akikazu; Shimoyama, Kazuhito; Monde, Masanori*; Ohshima, Hiroyuki

no journal, , 

Sodium reacts chemically with water in case of unexpected tube failure of steam generator (SG) in fast breeder reactor (FBR), exoergic reaction produced reaction field with high temperature and high corrosive (sodium-water reaction). Adjacent tubes in the field have possibility of rupture by inner pressure. It is integral to predict the event with high accuracy that we understand characteristics of heat transfer inside tube in detail. Experimental study has been carried out and clarify characteristics of heat flux and temperature on inner wall under low mass flow rate and high subcooling.

Oral presentation

Characteristics of heat transfer inside tube during sodium-water reaction in FBR steam generator

Kurihara, Akikazu; Ohshima, Hiroyuki; Monde, Masanori*

no journal, , 

Sodium reacts chemically with water in case of unexpected tube failure of steam generator (SG) in fast breeder reactor (FBR), exoergic reaction produced reaction field with high temperature and high corrosive (sodium-water reaction). Adjacent tubes are exposed to the reaction field and have possibility of overheating rupture by inner pressure with reduction of material strength. It is integral to predict the event with high accuracy that we understand characteristics of heat transfer inside tube in detail. Rapid heating experiment equivalent to sodium-water reaction has been carried out under high pressure, low mass flow rate and high subcooling, Heat flux and temperature on inner wall were estimated correctly by inverse problem solution. As the result of present study, we confirm adequate heat transfer correlations to evaluate overheating tube rupture.

Oral presentation

Rapid vapor generation during contact of a liquid droplet with a hot surface

Nishida, Takuya*; Mitsutake, Yuichi*; Monde, Masanori*; Kurihara, Akikazu

no journal, , 

Rapid vapor generation during impact of a single ethanol droplet on a hot surface was observed for well understanding of wetting phenomena. Photographs during a single droplet impacting on a surface at 190-210 $$^{circ}$$C were taken by a high speed digital camera with a microscope. Copper and carbon steel were used for the surface material. The liquid subcooling was varied from 10 to 50 K. The boiling situation changes from nucleate boiling to film boiling like as the boiling transition in pool boiling. Delay time to develop vapor film on the hot surface was measured from the observations. While the delay time increases with increase of subcooling and decrease of thermal inertia of the soild for the lower surface temperature, it shows constant for the higher surface temperature above the superheat limit of liquid.

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