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Journal Articles

Waste management in a Hot Laboratory of Japan Atomic Energy Agency, 2; Condensation and solidification experiments on liquid waste

Watanabe, So; Ogi, Hiromichi*; Shibata, Atsuhiro; Nomura, Kazunori

International Journal of Nuclear and Quantum Engineering (Internet), 13(4), p.169 - 174, 2019/04

As a part of STRAD project conducted by JAEA, condensation of radioactive liquid waste containing various chemical compounds using reverse osmosis (RO) membrane filter was examined for efficient and safety treatment of the liquid wastes accumulated inside hot laboratories. NH$$_{4}$$$$^{+}$$ ion in the feed solution was successfully concentrated, and NH$$_{4}$$$$^{+}$$ ion involved in the effluents became lower than target value; 100 ppm. Solidification of simulated aqueous and organic liquid wastes was also tested. Those liquids were successfully solidified by adding cement or coagulants. Nevertheless, optimization in materials for confinement of chemicals is required for long time storage of the final solidified wastes.

Journal Articles

ROSA/LSTF test on nitrogen gas behavior during reflux condensation in PWR and RELAP5 code analyses

Takeda, Takeshi; Otsu, Iwao

Mechanical Engineering Journal (Internet), 5(4), p.18-00077_1 - 18-00077_14, 2018/08

JAEA Reports

Data report of ROSA/LSTF experiment SB-HL-12; 1% Hot leg break LOCA with SG depressurization and gas inflow

Takeda, Takeshi

JAEA-Data/Code 2015-022, 58 Pages, 2016/01

JAEA-Data-Code-2015-022.pdf:3.31MB

The SB-HL-12 test simulated PWR 1% hot leg SBLOCA under assumptions of total failure of HPI system and non-condensable gas (nitrogen gas) inflow. SG depressurization by fully opening relief valves in both SGs as AM action was initiated immediately after maximum fuel rod surface temperature reached 600 K. After AM action due to first core uncovery by core boil-off, the primary pressure decreased, causing core mixture level swell. The fuel rod surface temperature then increased up to 635 K. Second core uncovery by core boil-off took place before LSC induced by steam condensation on ACC coolant injected into cold legs. The core liquid level recovered rapidly after LSC. The fuel rod surface temperature then increased up to 696 K. The pressure difference became larger between the primary and SG secondary sides after nitrogen gas inflow. Third core uncovery by core boil-off occurred during reflux condensation. The maximum fuel rod surface temperature exceeded 908 K.

JAEA Reports

Data report of ROSA/LSTF experiment SB-CL-32; 1% cold leg break LOCA with SG depressurization and no gas inflow

Takeda, Takeshi

JAEA-Data/Code 2014-021, 59 Pages, 2014/11

JAEA-Data-Code-2014-021.pdf:5.16MB

Experiment SB-CL-32 was conducted on May 28, 1996 using the LSTF. The experiment SB-CL-32 simulated 1% cold leg small-break LOCA in PWR under assumptions of total failure of HPI system and no inflow of non-condensable gas from ACC tanks. Secondary-side depressurization of both SGs as AM action to achieve the depressurization rate of 200 K/h in the primary system was initiated 10 min after break. Core uncovery started with liquid level drop in crossover leg downflow-side. The core liquid level recovered rapidly after first LSC. The surface temperature of simulated fuel rod then increased up to 669 K. Core uncovery took place before second LSC induced by steam condensation on ACC coolant. The core liquid level recovered rapidly after second LSC. The maximum fuel rod surface temperature was 772 K. The continuous core cooling was confirmed because of coolant injection by LPI system. This report summarizes the test procedures, conditions and major observation.

Journal Articles

Study on drop wise condensation by using functionalized heat transfer surface

Koizumi, Yasuo; Yoshizawa, Shota*

Proceedings of the ASME 2014 International Mechanical Engineering Congress and Exposition (IMECE 2014) (DVD-ROM), 7 Pages, 2014/11

The enhancement of drop wise condensation heat transfer by functionalizing a heat transfer surface was examined for 0.1 MPa steam. A gold-plated surface was used to produce the drop wise condensation. Rectangular-grooved heat transfer surfaces were adopted to functionalize the heat transfer surface. The size of the grooves were 2 mm $$times$$ 2 mm $$times$$ 2 mm, 3 mm $$times$$ 3 mm $$times$$ 3 mm and 2 mm $$times$$ 3 mm $$times$$ 2 mm (depth $$times$$ top width $$times$$ bottom width), respectively. The heat flux of the grooved surface was larger than that of the plain gold-plated surface. When the groove size was 2 mm $$times$$ 2 mm $$times$$ 2 mm and the top parts and the walls of grooves were plated with gold, the heat transfer rate augmentation was highest; the augmentation rate was 1.53. Since to increase the width of the top part of the grooves tended to bring the quality of the surface structure close to the plain surface, it was not right direction. It was also implied that to make summits and troughs on the surface to collect condensate tended to expose the summit part to steam more, which might result in the heat transfer augmentation.

Journal Articles

Roll wave effects on annular condensing heat transfer in horizontal PCCS condenser tube

Kondo, Masaya; Nakamura, Hideo; Anoda, Yoshinari; Saishu, Sadanori*; Obata, Hiroyuki*; Shimada, Rumi*; Kawamura, Shinichi*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 9 Pages, 2002/00

no abstracts in English

Journal Articles

Thermal-hydraulic research on future reactor systems in the ROSA program at JAERI

Yonomoto, Taisuke; Otsu, Iwao; Svetlov, S.*

Proceedings of 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-3), p.521 - 528, 2002/00

A research project is being conducted at the Japan Atomic Energy Research Institute on thermal hydraulics for the future reactor systems. The present paper provides the belief description of the project, followed by two recent topics: the natural circulation in the PWR loop and the condensation heat transfer for a passive cooling system. For the first topic, we discuss the importance of the modeling of the nonuniform flow behavior among SG U-tubes for the assessment of the long-term decay heat removal systems relying on the SG secondary side cooling. Such a system is planned to be used in APWR+, a Japanese next-generation PWR. The condensation heat transfer was investigated using the data obtained at the SPOT test facility in Russia. The results have shown that the measured heat transfer rates on the inner surface of the tube consisting of several bends and short straight sections can be predicted using the existing correlations with the accuracy of several percentage, although the correlations are based typically on the data taken using relatively long straight tube.

Journal Articles

Analysis of multi-dimensional boiling flow in secondary water pool of horizontal PCCS; Effect of pool size

Onuki, Akira; Nakamura, Hideo; Kawamura, Shinichi*; Saishu, Sadanori*

Nippon Kikai Gakkai Netsu Kogaku Koenkai Koen Rombunshu, p.31 - 32, 2001/11

A passive containment cooling system (PCCS) is under planning to use in a next-generation-type BWR for long-term cooling by condensing steam using horizontal heat exchangers. Heat transfer behavior in a secondary water pool is one of important phenomena governing heat removal performance of the PCCS. Boiling and condensation can be supposed under high heat flux regions and the characteristics of the two-phase natural circulation should be evaluated. This study investigated effects of pool size on the characteristics by multi-dimensional two-fluid model code ACE-3D. It was found from the analyses that the pool size gives no significant influences for the characteristics in tube bundle under local-boiling mode.

Journal Articles

Baseline study to model a typical condensation-induced water hammer event measured at the two-phase flow test facility (TPTF) in Japan

Schultz, R. R.*; Kondo, Masaya; Anoda, Yoshinari

Emerging Technologies for Fluids, Structures and Fluid-Structure Interaction, 2001 (PVP-Vol.431), p.1 - 12, 2001/07

no abstracts in English

Journal Articles

ACE-3D code analyses of multi-dimensional boiling flow in horizontal PCCS water pool

Onuki, Akira; Nakamura, Hideo; Anoda, Yoshinari; Obata, Hiroyuki*; Saishu, Sadanori*

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 10 Pages, 2001/00

A passive containment cooling system (PCCS) is under planning to use in a next-generation-type BWR for long-term cooling by condensing steam using horizontal heat exchangers. Heat transfer behavior in a secondary water pool is one of important phenomena governing heat removal performance of the PCCS. Boiling and condensation can be supposed under high heat flux regions and the two-phase natural circulation might enhance the heat transfer due to an increase of flow rate and a flow agitation. However, some heat transfer tubes might be covered only by steam and the heat transfer is degraded in such region (Steam-blanket effect). This study evaluated the characteristics of the heat transfer behavior in the secondary water pool by multi-dimensional two-fluid model code ACE-3D. It was found from the analyses that no any heat transfer tubes are covered only by steam and the heat transfer is enhanced due to the nucleate boiling and the increase of local liquid flow rate.

Journal Articles

Experimental investigation of thermal-hydraulic performance of PCCS with horizontal tube heat exchangers; Single U-tube test

Nakamura, Hideo; Anoda, Yoshinari; Tabata, Hiroaki*; Obata, Hiroyuki*; Arai, Kenji*; Kurita, Tomohisa*

JAERI-Conf 2000-015, p.177 - 184, 2000/11

no abstracts in English

Journal Articles

Analysis of steam-blanket effect in PCCS with horizontal heat exchanger

Onuki, Akira; Nakamura, Hideo; Anoda, Yoshinari

Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.258 - 263, 2000/00

no abstracts in English

Journal Articles

Single U-tube Testing and RELAP5 code analysis of PCCS with horizontal heat exchanger

Nakamura, Hideo; Kondo, Masaya; Asaka, Hideaki; Anoda, Yoshinari; Tabata, Hiroaki*; Obata, Hiroyuki*

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.336 - 343, 2000/00

no abstracts in English

Journal Articles

Analyses of CsI aerosol deposition in aerosol behavior tests in WIND project

Kudo, Tamotsu; Shibazaki, Hiroaki*; Hidaka, Akihide; Maruyama, Yu; Maeda, Akio; Harada, Yuhei; Hashimoto, Kazuichiro; Sugimoto, Jun; Yoshino, T.*; Suzuki, K.*

JAERI-Conf 99-005, p.197 - 201, 1999/07

no abstracts in English

Journal Articles

Vapor condensation and thermophoretic aerosol deposition of cesium iodide in horizontal thermal gradient pipes

Maruyama, Yu; Shibazaki, Hiroaki*; Igarashi, Minoru*; Maeda, Akio; Harada, Yuhei; Hidaka, Akihide; Sugimoto, Jun; Hashimoto, Kazuichiro*; Nakamura, Naohiko*

Journal of Nuclear Science and Technology, 36(5), p.433 - 442, 1999/05

 Times Cited Count:9 Percentile:40.81(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermofluid experiments on ingress of coolant event

Kunugi, Tomoaki; Takase, Kazuyuki; Kurihara, Ryoichi; Seki, Yasushi;

Fusion Engineering and Design, 42, p.67 - 72, 1998/00

 Times Cited Count:9 Percentile:37.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of residual heat removal process due to natural circulation in a water pool of a passive safety light water reactor

Onuki, Akira; Araya, Fumimasa;

PHOENICS J. Comput. Fluid Dyn. Its Appl., 9(3), p.326 - 342, 1996/09

no abstracts in English

Journal Articles

Application of simplified condensation model to PWR LBLOCA transient analysis with TRAC-PF1 code

; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.290 - 297, 1996/04

 Times Cited Count:3 Percentile:65.95(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Non-condensable gas effects in ROSA/AP600 small-break LOCA experiments

Nakamura, Hideo; Kukita, Yutaka; R.A.Shaw*; R.R.Schultz*

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART A), p.237 - 244, 1996/00

no abstracts in English

43 (Records 1-20 displayed on this page)