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JAEA Reports

Annual report of Nuclear Science Research Institute, JFY 2023

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.

JAEA Reports

Decrease in coolability events analysis for the safety assessment of JRR-3 silicide core by THYDE-W code

Kaminaga, Masanori; Yamamoto, Kazuyoshi

JAERI-Tech 97-016, 120 Pages, 1997/03

JAERI-Tech-97-016.pdf:3.76MB

no abstracts in English

JAEA Reports

Reactivity initiated events analysis for the safety assessment of JRR-3 silicide core by EUREKA-2 code

Kaminaga, Masanori

JAERI-Tech 97-014, 125 Pages, 1997/03

JAERI-Tech-97-014.pdf:4.04MB

no abstracts in English

JAEA Reports

Reactivity initiated events analysis for the safety assessment of JRR-4 silicide LEU core

Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nakano, Yoshihiro

JAERI-Tech 95-040, 79 Pages, 1995/07

JAERI-Tech-95-040.pdf:2.25MB

no abstracts in English

Journal Articles

Activities for operational safety of nuclear facilities in Japan

; Hirano, Masashi; Sobajima, Makoto; ;

IAEA-CN-61/2, 0, 14 Pages, 1995/00

no abstracts in English

JAEA Reports

Safety analysis of JMTR-LEU cores, 1; Reactivity initiated accident analysis

Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;

JAERI-M 92-095, 68 Pages, 1992/07

JAERI-M-92-095.pdf:1.52MB

no abstracts in English

JAEA Reports

Feedback control of primary circulation pump of PIUS-type reactor

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

JAERI-M 91-076, 34 Pages, 1991/05

JAERI-M-91-076.pdf:1.02MB

no abstracts in English

Journal Articles

Safety characteristics of the High Temperature Engineering Test Reactor

Shindo, Masami; ; Kunitomi, Kazuhiko; ; Sawa, Kazuhiro

Nucl. Eng. Des., 132, p.39 - 45, 1991/00

 Times Cited Count:5 Percentile:53.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Feedback control of primary circulation pump of PIUS-type reactor during startup and steady state operation

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

Thermal Hydraulics of Advanced Nuclear Reactors, p.85 - 89, 1990/11

no abstracts in English

Journal Articles

ROSA-IV large scale test facility(LSTF); Test program and first look of test results

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.

Journal Articles

Thermal-hydraulic transient characteristics of ship-propulsion reactor investigated through safety analysis

; ;

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

JAEA Reports

Oral presentation

Framework extension and operationalization of resilience engineering for practical implementation

Kitamura, Masaharu*; Oba, Kyoko; Yoshizawa, Atsufumi*

no journal, , 

no abstracts in English

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