Abstract
The power ramp tests performed at JMTR in Oarai R and D Center are objected to study the safety margin of the high burnup fuels. One of the important parameters measured during this test is the center temperature of the fuel pellet. For this measurement, a thermocouple is installed into the hole bored at the pellet center by the center boring device, which can fix the fuel pellet with the frozen CO{sub 2} gas during its boring process. At the Reactor Fuel Examination Facility (RFEF) in Tokai R and D Center, several improvements were applied for the previous boring device to gain its performance and reliability. The major improvements are the change of the drill bit, modification of the boring process and the optimization of the remote operability. The mock-up test will be performed with the irradiated fuel pellet to confirm the benefit of improvement. This study was conducted under a contract with the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI). (author)
Usami, Koji;
Onozawa, Atsushi;
Kimura, Yasuhiko;
Sakuraba, Naotoshi;
Shiina, Hidenori;
Harada, Akito;
Nakata, Masahito
[1]
- Japan Atomic Energy Agency, Nuclear Science Research Inst., Tokai, Ibaraki (Japan)
Citation Formats
Usami, Koji, Onozawa, Atsushi, Kimura, Yasuhiko, Sakuraba, Naotoshi, Shiina, Hidenori, Harada, Akito, and Nakata, Masahito.
Improvement of the center boring device for the irradiated fuel pellets.
Japan: N. p.,
2012.
Web.
Usami, Koji, Onozawa, Atsushi, Kimura, Yasuhiko, Sakuraba, Naotoshi, Shiina, Hidenori, Harada, Akito, & Nakata, Masahito.
Improvement of the center boring device for the irradiated fuel pellets.
Japan.
Usami, Koji, Onozawa, Atsushi, Kimura, Yasuhiko, Sakuraba, Naotoshi, Shiina, Hidenori, Harada, Akito, and Nakata, Masahito.
2012.
"Improvement of the center boring device for the irradiated fuel pellets."
Japan.
@misc{etde_22078617,
title = {Improvement of the center boring device for the irradiated fuel pellets}
author = {Usami, Koji, Onozawa, Atsushi, Kimura, Yasuhiko, Sakuraba, Naotoshi, Shiina, Hidenori, Harada, Akito, and Nakata, Masahito}
abstractNote = {The power ramp tests performed at JMTR in Oarai R and D Center are objected to study the safety margin of the high burnup fuels. One of the important parameters measured during this test is the center temperature of the fuel pellet. For this measurement, a thermocouple is installed into the hole bored at the pellet center by the center boring device, which can fix the fuel pellet with the frozen CO{sub 2} gas during its boring process. At the Reactor Fuel Examination Facility (RFEF) in Tokai R and D Center, several improvements were applied for the previous boring device to gain its performance and reliability. The major improvements are the change of the drill bit, modification of the boring process and the optimization of the remote operability. The mock-up test will be performed with the irradiated fuel pellet to confirm the benefit of improvement. This study was conducted under a contract with the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI). (author)}
place = {Japan}
year = {2012}
month = {Mar}
}
title = {Improvement of the center boring device for the irradiated fuel pellets}
author = {Usami, Koji, Onozawa, Atsushi, Kimura, Yasuhiko, Sakuraba, Naotoshi, Shiina, Hidenori, Harada, Akito, and Nakata, Masahito}
abstractNote = {The power ramp tests performed at JMTR in Oarai R and D Center are objected to study the safety margin of the high burnup fuels. One of the important parameters measured during this test is the center temperature of the fuel pellet. For this measurement, a thermocouple is installed into the hole bored at the pellet center by the center boring device, which can fix the fuel pellet with the frozen CO{sub 2} gas during its boring process. At the Reactor Fuel Examination Facility (RFEF) in Tokai R and D Center, several improvements were applied for the previous boring device to gain its performance and reliability. The major improvements are the change of the drill bit, modification of the boring process and the optimization of the remote operability. The mock-up test will be performed with the irradiated fuel pellet to confirm the benefit of improvement. This study was conducted under a contract with the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI). (author)}
place = {Japan}
year = {2012}
month = {Mar}
}