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Journal Articles

The OECD/NEA Working Group on the Analysis and Management of Accidents (WGAMA); Advances in codes and analyses to support safety demonstration of nuclear technology innovations

Nakamura, Hideo; Bentaib, A.*; Herranz, L. E.*; Ruyer, P.*; Mascari, F.*; Jacquemain, D.*; Adorni, M.*

Proceedings of International Conference on Topical Issues in Nuclear Installation Safety; Strengthening Safety of Evolutionary and Innovative Reactor Designs (TIC 2022) (Internet), 10 Pages, 2022/10

JAEA Reports

Chaotic behavior in a system simulating the pressure balanced injection system; Analysis of passive safety reactor behavior, JAERI's nuclear research promotion program, H12-012 (Contract research)

Madarame, Haruki*; Okamoto, Koji*; Tanaka, Gentaro*; Morimoto, Yuichiro*; Sato, Akira*; Kondo, Masaya

JAERI-Tech 2003-017, 156 Pages, 2003/03

JAERI-Tech-2003-017.pdf:5.31MB

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

Thermal hydraulic research on next generation PWR's using ROSA/LSTF

Yonomoto, Taisuke; Anoda, Yoshinari

IAEA-TECDOC-1149, p.233 - 246, 2000/05

no abstracts in English

JAEA Reports

Status and subjects of thermal-hydraulic analysis for next-generation LWRs

Subcommittee on Improvement of Reactor Thermal-Hydraulic Analysis Codes

JAERI-Review 2000-002, p.105 - 0, 2000/03

JAERI-Review-2000-002.pdf:6.24MB

no abstracts in English

Journal Articles

ROSA/LSTF experiments on low-pressure natural circulation heat removal for next-generation PWRs

Yonomoto, Taisuke; Otsu, Iwao

Proceedings of 12th Pacific Basin Nuclear Conference (PBNC 2000), Vol.1, p.317 - 329, 2000/00

no abstracts in English

Journal Articles

Status and subjects of thermal-hydraulic analysis for next-generation LWRs with passive safety systems

Aritomi, Masanori*; Onuki, Akira; Arai, Kenji*; ; Yonomoto, Taisuke; Araya, Fumimasa; Akimoto, Hajime

Nihon Genshiryoku Gakkai-Shi, 41(7), p.738 - 757, 1999/00

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal-hydraulic research on passive safety systems for next-generation PWRs using ROSA/LSTF

Yonomoto, Taisuke

NUREG/CP-0166, 3, p.31 - 52, 1998/00

no abstracts in English

Journal Articles

Advantage of modified JAERI passive safety reactor (JPSR-II)

Murao, Yoshio; Ochiai, Masaaki

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 2, p.1075 - 1085, 1997/00

no abstracts in English

Journal Articles

Design and evaluation methods for a water cooling panel system for decay heat removal from a high-temperature gas-cooled reactor

Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio

Heat Transfer-Jpn. Res., 26(3), p.159 - 175, 1997/00

no abstracts in English

Journal Articles

Safety analyses of a passive safety light water reactor JPSR

Araya, Fumimasa; Iwamura, Takamichi; Yoshida, Hiroyuki; Kunii, Katsuhiko; Okumura, Keisuke; Murao, Yoshio

10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.299 - 305, 1996/00

no abstracts in English

Journal Articles

Passive heat removal by vessel cooling system of HTTR during no forced cooling accidents

Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Shinozaki, Masayuki

Nucl. Eng. Des., 166(2), p.179 - 190, 1996/00

 Times Cited Count:21 Percentile:83.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Passive safety injection experiments with a large-scale pressurized water reactor simulator

Yonomoto, Taisuke; Kukita, Yutaka; Anoda, Yoshinari;

Nuclear Technology, 109, p.338 - 345, 1995/03

 Times Cited Count:10 Percentile:68.99(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF gravity-driven safety injection experiment Run SB-CL-27

Yonomoto, Taisuke; ; ; Anoda, Yoshinari; Kukita, Yutaka; ; Ito, Hideo; Osaki, Hideki; ; Nishikizawa, Tomotoshi; et al.

JAERI-M 94-069, 145 Pages, 1994/03

JAERI-M-94-069.pdf:4.07MB

no abstracts in English

Journal Articles

Passive safety injection experiments with a large-scale PWR simulator

Yonomoto, Taisuke; Kukita, Yutaka; Anoda, Yoshinari;

Proc. of ARS 94 Int. Topical Meeting on Advansed Reactors safety, 1, p.216 - 223, 1994/00

no abstracts in English

Oral presentation

Development of detailed temperature analysis model for a scale model of HTGR vessel cooling system

Teramachi, Yuhei*; Sawa, Kazuhiro*; Ishitsuka, Etsuo; Ho, H. Q.

no journal, , 

17 (Records 1-17 displayed on this page)
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