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

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.

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

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

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

https://doi.org/10.1016/0029-5493(96)01268-X

no abstracts in English

Prediction of developing bubbly flow along a large vertical pipe by multidimensional two-fluid model; Development of multidimensional two-fluid model code and analysis under a low velocity

Onuki, Akira; Kamo, Hideki*;

Proceedings of Japan-US Seminar on Two-Phase Flow Dynamics, 0, p.75 - 82, 1996/00

no abstracts in English

A Concept of passive safety pressurized water reactor system with inherent matching nature of core heat generation and heat removal

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

Journal of Nuclear Science and Technology, 32(9), p.855 - 867, 1995/09

https://doi.org/10.3327/jnst.32.855

no abstracts in English

MRX(marine reactor X)

Hoshi, Tatsuo

Nihon Genshiryoku Gakkai-Shi, 37(9), p.792 - 794, 1995/00

no abstracts in English

Concept of passive safety light water reactor system (JPSR)

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.723 - 728, 1995/00

no abstracts in English

Analysis of system thermal hydraulic responses for passive safety injection experiment at ROSA-IV/Large Scale Test Facility using JAERI modified version of RELAP5/MOD2 code

; Yonomoto, Taisuke; Kukita, Yutaka

Journal of Nuclear Science and Technology, 31(12), p.1265 - 1274, 1994/12

https://doi.org/10.3327/jnst.31.1265

no abstracts in English