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Hirooka, Shun; Horii, Yuta; Hayashizaki, Kohei; Mohamad, A. B.
Kaku Nenryo, (60-1), p.17 - 20, 2025/02
no abstracts in English
Mohamad, A. B.; Udagawa, Yutaka
Nuclear Technology, 210(2), p.245 - 260, 2024/02
Times Cited Count:2 Percentile:43.92(Nuclear Science & Technology)Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*
Corrosion Science, 224, p.111540_1 - 111540_15, 2023/11
Times Cited Count:6 Percentile:52.51(Materials Science, Multidisciplinary)Mohamad, A. B.; Nakajima, Kunihisa; Miwa, Shuhei; Osaka, Masahiko
Journal of Nuclear Science and Technology, 60(3), p.215 - 222, 2023/03
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*
no journal, ,
Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*
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Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.
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no abstracts in English
Journeau, C.*; Bechta, S.*; Komlev, A.*; Kurata, Masaki; Ohgi, Hiroshi; Matsumoto, Toshinori; Mohamad, A. B.; Barrachin, M.*; Quaini, A.*; Bottomley, D.*; et al.
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Yamashita, Shinichiro; Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; et al.
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JAEA is conducting research on various coating technologies for fuel cladding tubes aimed at improving accident resistance. In the lecture, we will introduce new equipment development at JAEA aimed at using these studies in addition to an overview of the entire project.
Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*
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Mohamad, A. B.; Soma, Yasutaka; Nemoto, Yoshiyuki; Abe, Yosuke; Ioka, Ikuo; Sato, Tomonori; Ishijima, Yasuhiro; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.
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Japan Atomic Energy Agency (JAEA) has launched fundamental researches on zircalloy with accident tolerance since 2019. The main purposes of the fundamental researches are to deepen the understanding of the zircalloy behavior under long-term normal operation or Loss of Coolant Accident (LOCA), beyond design basis accident (B-DBA) and severe accident (SA) conditions, and to support the implementation of Cr-coated zircalloy which is being developed by Japanese vendor. JAEA has also been conducted basic technology developments which is necessary for the understanding of the behavior of accident tolerant coated-zircalloy under normal operation, LOCA, B-DBA and SA conditions. For example, the ion irradiation technique combined with light water reactor (LWR) coolant conditions is being developed to simulate the normal operation condition. In addition, to understand LOCA phenomena, the results obtained from the LOCA test are implemented in the machine learning to understand in more detail the cladding fracture and ballooning. Furthermore, a separate effect test, such as the high temperature oxidation test, is also carried out. The fission product release during the B-DBA and SA are also included in the research program. The research results obtained by using these basic technologies will be integrated and implemented into the fuel performance analysis code to predict the fuel performance under reactor operating conditions.
Yamashita, Shinichiro; Mohamad, A. B.; Soma, Yasutaka; Nemoto, Yoshiyuki; Ioka, Ikuo; Kaji, Yoshiyuki; Osaka, Masahiko
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Japan's Accident Tolerant Fuel (ATF) research and development (R&D) program has been conducted since 2015 in cooperation with power plant providers, fuel venders and universities for making the most use of the experiences in R&D, practical design, and evaluations of fuels and cores of commercial Light Water Reactors (LWRs). An overview of the present R&D progress is given, including the role of Japan Atomic Energy Agency (JAEA) in the program.
Miwa, Shuhei; Nakajima, Kunihisa; Karasawa, Hidetoshi; Rizaal, M.; Luu, V. N.; Mohamad, A. B.
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no abstracts in English
Journeau, C.*; Bechta, S.*; Komlev, A.*; Kurata, Masaki; Ogi, Hiroshi; Matsumoto, Toshinori; Mohamad, A. B.; Barrachin, M.*; Quaini, A.*; Guneau, C.*; et al.
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Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.
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JAEA is promoting the characterization of various coating tubes as part of fundamental research that contributes to the practical application of coated fuel cladding aiming at improving accident tolerance. In this presentation, overall outline, the new test equipment under construction, and highlight results of the vapor oxidation characteristic evaluation test for coated claddings will be presented.
Mohamad, A. B.; Chen, J.*; Ioka, Ikuo; Yamashita, Shinichiro
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no abstracts in English
Mohamad, A. B.; Yamashita, Shinichiro; Soma, Yasutaka; Nemoto, Yoshiyuki; Pham, V. H.; Abe, Yosuke; Ioka, Ikuo; Sato, Tomonori; Ishijima, Yasuhiro; Miwa, Shuhei; et al.
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Mohamad, A. B.; Okada, Yuji*; Sato, Daiki*; Ioka, Ikuo; Suzuki, Eriko; Nemoto, Yoshiyuki
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Nemoto, Yoshiyuki; Okada, Yuji*; Sato, Daiki*; Mohamad, A. B.; Ioka, Ikuo; Suzuki, Eriko
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no abstracts in English
Tezuka, Kenichi*; Kino, Chiaki*; Yamashita, Susumu; Mohamad, A. B.; Nemoto, Yoshiyuki
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no abstracts in English