Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Soma, Shu; Ishigaki, Masahiro*; Abe, Satoshi; Shibamoto, Yasuteru
Nuclear Engineering and Design, 416, p.112754_1 - 112754_18, 2024/01
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Soma, Shu; Ishigaki, Masahiro*; Abe, Satoshi; Shibamoto, Yasuteru
Nuclear Engineering and Technology, 10 Pages, 2024/00
Soma, Shu; Abe, Satoshi; Shibamoto, Yasuteru; Ishigaki, Masahiro*
Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 13 Pages, 2022/03
Ebana, Minoru; Nomura, Yukihiro; Watanabe, Toshiyuki; Shirai, Kenji; Otaka, Tadashi; Soma, Susumu; Jin, Kazumi; Sumiya, Shuichi; Fukasawa, Kunio
PNC TN8530 87-004, 196 Pages, 1987/09
no abstracts in English
Umino, Hideo*; Katsuta, Hiroji*; Ito, Kazuaki*; Soma, Mitsue*; Yamamoto, Shunya; Takano, Katsuyoshi; Yoshikawa, Masahito
no journal, ,
TiO powder doped with sulfur and nitrogen has been studied for the synthesis of photocatalyst working under the visible light. Samples were synthesized by heart treatment of titanium disulfide powders at temperatures range from 400 to 650
C in nitrogen, oxygen and ammonia mixtures using an electric furnace. The crystalline structure of sample powders heat-treated at 400C shows anatase and rutile structures and then changes to rutile structure at 650C. The optical absorption at visible light region was observed in the sample powders heat-treated at temperatures range from 400 to 500C. Furthermore, photocatalytic reaction of the synthesized powders using visible light was confirmed by decomposition of 2-propanol. We decided the synthetic condition of visible-light-responding photocatalyst.
-ray spectrometerSaito, Kei; Takashima, Hideki; Emori, Shuichi; Soma, Susumu; Takada, Chie
no journal, ,
no abstracts in English
Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.
no journal, ,
no abstracts in English
Soma, Shu; Abe, Satoshi; Shibamoto, Yasuteru
no journal, ,
no abstracts in English
Yamashita, Shinichiro; Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; et al.
no journal, ,
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.; Soma, Yasutaka; Nemoto, Yoshiyuki; Abe, Yosuke; Ioka, Ikuo; Sato, Tomonori; Ishijima, Yasuhiro; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.
no journal, ,
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.
