Zobrazeno 1 - 10
of 56
pro vyhledávání: '"Shohei Ueta"'
Autor:
Asset Shaimerdenov, Shamil Gizatulin, Daulet Dyussambayev, Saulet Askerbekov, Shohei Ueta, Jun Aihara, Taiju Shibata, Nariaki Sakaba
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 8, Pp 2792-2800 (2022)
In the core of the WWR-K reactor, a long-term irradiation of tristructural isotopic (TRISO)-coated fuel particles (CFPs) with a UO2 kernel was carried out under high-temperature gas-cooled reactor (HTGR)-like operating conditions. The temperature of
Externí odkaz:
https://doaj.org/article/49c7915f1ef34e53b84f4cb2dc9b8f3d
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00571-19-00571 (2020)
JAEA has been progressing to design HTGR fuels for not only small-type practical HTGRs but also VHTR proposed in GIF which can be utilized for various purposes with high-temperature heat at 750 to 950 °C. To increase economy of these HTGRs, JAEA has
Externí odkaz:
https://doaj.org/article/23591791aa7c4d3b80b5f8d5efe763c9
Publikováno v:
Mechanical Engineering Journal, Vol 5, Iss 5, Pp 18-00084-18-00084 (2018)
To develop Pu-burner high temperature gas-cooled reactor (HTGR) attaining very high burn-up around 500 GWd/t, the security and safety fuel (3S-TRISO fuel) is proposed. The 3S-TRISO fuel employs the coated fuel particle with a fuel kernel made of plut
Externí odkaz:
https://doaj.org/article/f82cdc398d9e471c9703ef6af6914994
Publikováno v:
International Journal of Applied Ceramic Technology. 20:261-265
Publikováno v:
Ceramics International. 48:8706-8708
Publikováno v:
Nuclear Technology. 208:335-346
When total volume control is applied to toxicity in nuclear waste management it becomes a limiting factor for the permittable total operating capacity of nuclear reactors. An alternative conceptual...
Publikováno v:
Journal of the Atomic Energy Society of Japan. 63:615-620
Autor:
Yukio Tachibana, Minoru Goto, Naoki Mizuta, Jun Aihara, Koji Okamoto, Shohei Ueta, Masaki Honda
Publikováno v:
Journal of Nuclear Science and Technology. 58:107-116
The concept of Pu-burner high temperature gas-cooled reactor (HTGR) has been proposed to more safely reduce the amount of recovered Pu. In the Pu-burner HTGR concept, coated fuel particles with ZrC...
Publikováno v:
Scopus-Elsevier
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00571-19-00571 (2020)
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00571-19-00571 (2020)
JAEA has been progressing to design HTGR fuels for not only small-type practical HTGRs but also VHTR proposed in GIF which can be utilized for various purposes with high-temperature heat at 750 to 950 °C. To increase economy of these HTGRs, JAEA has
Study on evaluation method of kernel migration of TRISO fuel for High Temperature Gas-cooled Reactor
Autor:
Yuji Fukaya, Shoichiro Okita, Koei Sasaki, Shohei Ueta, Minoru Goto, Hirofumi Ohashi, Xing L. Yan
Publikováno v:
Nuclear Engineering and Design. 399:112033