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Journal Articles

The HTTR project as the world leader of HTGR research and development

Shiozawa, Shusaku; Komori, Yoshihiro; Ogawa, Masuro

Nihon Genshiryoku Gakkai-Shi, 47(5), p.342 - 349, 2005/05

http://ci.nii.ac.jp/naid/10014336574

For the purpose to extend high temperature nuclear heat application, JAERI constructed the HTTR, High Temperature Engineering Test Reactor, and has carried out research and development of high temperature gas cooled reactor system aiming at high efficiency power generation and hydrogen production. This paper explains the history, main results, present status of research and development of HTTR project, international cooperation of research and development of HTGR and future plan aiming at development of Japanese original future HTGR-Hydrogen production system. This paper includes results from the study, which is entrusted from Ministry of Education, Culture, Sports, Science and Technology of Japan.

JAEA Reports

Report on the Status and Future Upgrades of the Facilities and Instruments in the JRR-3

Subcommittee for Neutron Beam Utilization; Status and Future Upgrades of the Facilities and Instruments

JAERI-Review 2003-037, 88 Pages, 2004/02

JAERI-Review-2003-037.pdf:6.98MB

The refurbished JRR-3 reached critical in March 1990, and the facilities were opened to the general user program in June 1991. Since then the improved specification and the increase of the beam flux of JRR-3 made it recognized as one of the top four research reactors in the world. Despite the ten fruitful years of achievements in research activities performed at JRR-3, it is indispensable to continuously upgrade and improve research facilities in order to maintain our standard of excellence in the research activities. It is also important that the high intensity proton accelerator project (J-PARC project) is progressing in the same JAERI site. Under these circumstances surrounding the JRR-3 facility, a task force under the neutron beam utilization committee was formed in 2001 and assigned to recommend the necessary upgrade and improvements of reactor facilities as well as neutron scattering instruments in JRR-3. This report summarizes analysis and discussions carried out in the task force during these two years, and describes recommendations from the task force.

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.

JAEA Reports