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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.
Udagawa, Yutaka; Fuketa, Toyoshi*
Comprehensive Nuclear Materials, 2nd Edition, Vol.2, p.322 - 338, 2020/08
Chikazawa, Yoshitaka; Kato, Atsushi; Nabeshima, Kunihiko; Otaka, Masahiko; Uzawa, Masayuki*; Ikari, Risako*; Iwasaki, Mikinori*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05
Design study and evaluation for SDC and safety SDG on the BOP of the demonstration JSFR including fuel handling system, power supply system, component cooling water system, building arrangement are reported. For the fuel handling system, enhancement of storage cooling system has been investigated adding diversified cooling systems. For the power supply, existing emergency power supply system has been reinforced and alternative emergency power supply system is added. For the component cooling system and air conditioning, requirements and relation between safety grade components are investigated. Additionally for the component cooling system, design impact when adding decay heat removal system by sea water has been investigated. For reactor building, over view of evaluation on the external events and design policy for distributed arrangement is reported. Those design study and evaluation provides background information of SDC and SDG.
Sawa, Kazuhiro; Ueta, Shohei; Iyoku, Tatsuo
Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 10 Pages, 2003/09
This paper provides present status of research and development for the coated fuel particle (CFPs) including the advanced ZrC-CFP. Current HTGR employs so-called TRISO-CFPs with SiC layer. In safety design of the HTGR fuels, it is important to retain fission products within CFPs so that their release to primary coolant does not exceed an acceptable level. The behavior of TRISO-CFPs has been investigated through experiments and reactor operation. These data show excellent performance of the TRISO-CFPs when they are correctly fabricated. On the other hand, the crystalline material comprising the SiC layer has a tendency to decompose at high temperature. The transition temperatures of beta-SiC (as-deposited) to alpha-SiC vary from 1600 to 2200
C. ZrC is one of the transition metal carbides which are characterized by the high melting point and the thermodynamic stability etc. The CFPs with CVD-ZrC coatings have been investigated including the fabrication processes and characterization techniques developments.
Sawa, Kazuhiro; Suzuki, Shuichi*; Shiozawa, Shusaku
Nuclear Engineering and Design, 208(3), p.305 - 313, 2001/09
Times Cited Count：41 Percentile：92.42(Nuclear Science & Technology)no abstracts in English
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
Kugo, Teruhiko; Nakakawa, Masayuki
PHYSOR 96: Int. Conf. on the Physics of Reactors, 1, p.B73 - B81, 1996/00
no abstracts in English
Kunitomi, Kazuhiko; Shiozawa, Shusaku; Baba, Osamu
Proc. of ASME
JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.303 - 307, 1996/00
no abstracts in English
Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nakano, Yoshihiro
JAERI-Tech 95-040, 79 Pages, 1995/07
no abstracts in English
Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Murakami, Tomoyuki*; Fujii, Sadao*
Nucl. Eng. Des., 152, p.183 - 196, 1994/00
Times Cited Count：15 Percentile：75.28(Nuclear Science & Technology)no abstracts in English
Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;
JAERI-M 92-095, 68 Pages, 1992/07
no abstracts in English
Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;
JAERI-M 92-042, 92 Pages, 1992/03
no abstracts in English
Hayashi, Kimio; Shiozawa, Shusaku; Shindo, Masami; Iyoku, Tatsuo; *; Kikuchi, Takayuki; Sawa, Kazuhiro; Nakagawa, Shigeaki; Kashimura, Satoru; ; et al.
JAERI-M 91-140, 61 Pages, 1991/09
no abstracts in English
Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru
Energy, 16(1-2), p.449 - 458, 1991/00
Times Cited Count：4 Percentile：55.37(Thermodynamics)no abstracts in English
