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Narukawa, Takafumi; Kondo, Keietsu; Fujimura, Yuki; Kakiuchi, Kazuo; Udagawa, Yutaka; Nemoto, Yoshiyuki
Journal of Nuclear Materials, 582, p.154467_1 - 154467_12, 2023/08
Narukawa, Takafumi; Hamaguchi, Shusuke*; Takata, Takashi*; Udagawa, Yutaka
Proceedings of Asian Symposium on Risk Assessment and Management 2022 (ASRAM 2022) (Internet), 11 Pages, 2022/12
Narukawa, Takafumi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 63(11), p.780 - 785, 2021/11
no abstracts in English
Narukawa, Takafumi; Udagawa, Yutaka
Proceedings of TopFuel 2021 (Internet), 10 Pages, 2021/10
Nagase, Fumihisa; Narukawa, Takafumi; Amaya, Masaki
JAEA-Review 2020-076, 129 Pages, 2021/03
JAEA-Review-2020-076.pdf:3.9MB
Each light-water reactor (LWR) is equipped with the Emergency Core Cooling System (ECCS) to maintain the coolability of the reactor core and to suppress the release of radioactive fission products to the environment even in a loss-of-coolant accident (LOCA) caused by breaks in the reactor coolant pressure boundary. The acceptance criteria for ECCS have been established in order to evaluate the ECCS performance and confirm the sufficient safety margin in the evaluation. The limits defined in the criteria were determined in 1975 and reviewed based on state-of-the-art knowledge in 1981. Though the fuel burnup extension and necessary improvements of cladding materials and fuel design have been conducted, the criteria have not been reviewed since then. Meanwhile, much technical knowledge has been accumulated regarding the behavior of high-burnup fuel during LOCAs and the applicability of the criteria to the high-burnup fuel. This report provides a comprehensive review of the history and technical bases of the current criteria and summarizes state-of-the-art technical findings regarding the fuel behavior during LOCAs. The applicability of the current criteria to the high-burnup fuel is also discussed.
Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 57(7), p.782 - 791, 2020/07
Times Cited Count：3 Percentile：44.39(Nuclear Science & Technology)Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 57(1), p.68 - 78, 2020/01
Times Cited Count：1 Percentile：13.41(Nuclear Science & Technology)Narukawa, Takafumi; Amaya, Masaki
Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.912 - 921, 2019/09
Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 56(7), p.650 - 660, 2019/07
Times Cited Count：10 Percentile：80.35(Nuclear Science & Technology)Narukawa, Takafumi
Kaku Nenryo, (54-2), P. 3, 2019/07
no abstracts in English
Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10
Narukawa, Takafumi; Yamaguchi, Akira*; Jang, S.*; Amaya, Masaki
Proceedings of 14th International Conference on Probabilistic Safety Assessment and Management (PSAM-14) (USB Flash Drive), 10 Pages, 2018/09
Narukawa, Takafumi
Kaku Nenryo, (53-2), P. 5, 2018/08
no abstracts in English
Narukawa, Takafumi; Yamaguchi, Akira*; Jang, S.*; Amaya, Masaki
Nuclear Engineering and Design, 331, p.147 - 152, 2018/05
Times Cited Count：1 Percentile：12.83(Nuclear Science & Technology)Narukawa, Takafumi; Yamaguchi, Akira*; Jang, S.*; Amaya, Masaki
Journal of Nuclear Materials, 499, p.528 - 538, 2018/02
Times Cited Count：5 Percentile：50.9(Materials Science, Multidisciplinary)Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori
Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09
Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 53(11), p.1758 - 1765, 2016/11
Times Cited Count：9 Percentile：68.22(Nuclear Science & Technology)Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori
Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), p.53 - 62, 2016/09
In order to evaluate adequacy of present safety criteria and safety margins in terms of advanced fuels and provide a database for future regulation on them, JAEA started an extensive research program called ALPS-II program, which has been sponsored by NRA, Japan. This program is primarily composed of tests simulating a RIA and a LOCA on the high-burnup advanced fuels irradiated in commercial PWR or BWR. Recently, the failure limits of the high-burnup advanced fuels under RIA conditions were investigated at NSRR, and post-test examinations on the fuel rods after the pulse irradiation tests are being performed. In terms of the simulated LOCA test, integral thermal shock tests and high temperature oxidation tests were carried out at RFEF, and the fracture limits, high temperature oxidation rate, etc. of the high-burnup advanced fuel cladding were investigated. This paper mainly describes some recent experimental results obtained in this program with respect to RIA and LOCA.
Wu, H.; Udagawa, Yutaka; Narukawa, Takafumi; Amaya, Masaki
Nuclear Engineering and Design, 303, p.25 - 30, 2016/07
Times Cited Count：3 Percentile：30.54(Nuclear Science & Technology)Wu, H.; Udagawa, Yutaka; Narukawa, Takafumi; Amaya, Masaki
Nuclear Engineering and Design, 300, p.249 - 255, 2016/04
Times Cited Count：3 Percentile：30.54(Nuclear Science & Technology)