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Nagasumi, Satoru; Hasegawa, Toshinari; Nakagawa, Shigeaki; Kubo, Shinji; Iigaki, Kazuhiko; Shinohara, Masanori; Saikusa, Akio; Nojiri, Naoki; Saito, Kenji; Furusawa, Takayuki; et al.
JAEA-Research 2025-005, 23 Pages, 2025/07
JAEA-Research-2025-005.pdf:2.68MB
A safety demonstration test under abnormal operating conditions using the HTTR (High Temperature Engineering Test Reactor) was conducted to demonstrate safety features of the HTGRs (High Temperature Gas-cooled Reactors). Under a simulation of a control rod shutdown failure, all primary helium gas circulators were intentionally stopped during a steady-state operation at 100% reactor thermal power (30 MW), temporal changes of the reactor power and temperatures around the reactor pressure vessel (RPV) were obtained after the complete loss of forced heat removal from the reactor core. After the event (primary coolant flow stopped), the reactor power quickly decreased due to the negative reactivity feedback associated with the core temperature rise, and then the reactor power spontaneously shifted to a stable state of low power (about 1.2%) even after a recriticality. Heat dissipation from RPV surface to a surrounding vessel cooling system (water-cooled panels) ensured the amount of heat removal required to maintain the reactor temperature constant in the low power state. In this way, the transition from the event occurrence to the stable and safety state, i.e., inherent safety features of HTGRs, were demonstrated in the case of core forced cooling loss without active shutdown operations.
Nuclear Science Research Institute
JAEA-Review 2024-058, 179 Pages, 2025/03
JAEA-Review-2024-058.pdf:7.42MB
Nuclear Science Research Institute (NSRI) is composed of Planning and Management Department and six departments, namely Department of Operational Safety Administration, Department of Radiation Protection, Engineering Services Department, Department of Research Reactor and Tandem Accelerator, Department of Criticality and Hot Examination Technology and Department of Decommissioning and Waste Management, and each department manages facilities and develops related technologies to achieve the "Medium- to Long-term Plan" successfully and effectively. And, four research centers which are Advanced Science Research Center, Nuclear Science and Engineering Center, Nuclear Engineering Research Collaboration Center and Materials Sciences Research Center, belong to NSRI. In order to contribute the future research and development and to promote management business, this annual report summarizes information on the activities of NSRI of JFY 2023 as well as the activity on research and development carried out by Collaborative Laboratories for Advanced Decommissioning Science, Nuclear Safety Research Center and activities of Nuclear Human Resource Development Center, using facilities of NSRI.
Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Shiozawa, Shusaku
Nuclear Engineering and Design, 233(1-3), p.235 - 249, 2004/10
Times Cited Count：13 Percentile：62.40(Nuclear Science & Technology)JAERI conducted the safety evaluation of the HTTR considering various characteristics of the HTGR in order to confirm the adequacy of safety in all operational states. This paper describes the procedure and results of the safety evaluation especially focusing on the depressurization accident together with brief description of their analytical tools. Also, it presents topics in the regulatory review and Research and Development needs for the safety evaluation of future HTGRs.
Kaminaga, Masanori; Yamamoto, Kazuyoshi
JAERI-Tech 97-016, 120 Pages, 1997/03
no abstracts in English
Kaminaga, Masanori
JAERI-Tech 97-014, 125 Pages, 1997/03
no abstracts in English
Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nakano, Yoshihiro
JAERI-Tech 95-040, 79 Pages, 1995/07
no abstracts in English
; Hirano, Masashi; Sobajima, Makoto; ;
IAEA-CN-61/2, 0, 14 Pages, 1995/00
no abstracts in English
Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;
JAERI-M 92-095, 68 Pages, 1992/07
no abstracts in English
; Anoda, Yoshinari; Murata, Hideo; Yonomoto, Taisuke; ; Kukita, Yutaka
JAERI-M 91-076, 34 Pages, 1991/05
no abstracts in English
Shindo, Masami; ; Kunitomi, Kazuhiko; ; Sawa, Kazuhiro
Nucl. Eng. Des., 132, p.39 - 45, 1991/00
Times Cited Count：5 Percentile：53.27(Nuclear Science & Technology)no abstracts in English
; Anoda, Yoshinari; Murata, Hideo; Yonomoto, Taisuke; Kukita, Yutaka;
Thermal Hydraulics of Advanced Nuclear Reactors, p.85 - 89, 1990/11
no abstracts in English
Tasaka, Kanji; Koizumi, Yasuo
Nihon Genshiryoku Gakkai-Shi, 29(1), p.18 - 30, 1987/01
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)The Large Scal Test Facility (LSTF) of the Rig of Safety Assessment (ROSA)-IV program is an integral test fcility to investigate thermal-hydraulic response of a pressurized water reactor (PWR) system during small break loss-of-coolant accidents (LOCAs) and operational transients.
; ;
Nihon Genshiryoku Gakkai-Shi, 28(9), p.838 - 849, 1986/00
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
;
JAERI-M 9398, 147 Pages, 1981/03
no abstracts in English
Kitamura, Masaharu*; Oba, Kyoko; Yoshizawa, Atsufumi*
no journal, ,
no abstracts in English
