TY - GEN
T1 - Development of the cooling technology on TRU fuel pin bundle during fuel fabrication process :(1) Whole study plan and fabrication of test apparatuses
AU - Itoh, Kunihiro
AU - Ikeda, Kazuo
AU - Hishida, Koichi
AU - Kuroda, Taichiro
AU - Yamaguchi, Akira
AU - Takata, Takashi
PY - 2008
Y1 - 2008
N2 - The development of the fast reactor (FR) cycle is being preceded in Japan to utilize the plutonium and trans-uranium (TRU) efficiently. As the fuel generates heat due to decay of the TRU, it is required to develop an efficient system for cooling of the wire wrapped fuel pin bundle during the fabrication process where the bundle is being laid in horizontal state. To meet the requirement the four year study has started in 2006 sponsored by the Japanese government. In the first year the fabrications of the full mock-up and the enlarged- partial model were completed and the steady state heat removal tests have been performed. The temperature distribution data in the fuel bundle have been obtained and analyses have been also performed to compare with those measured data. The steady state experiments have revealed that the air cooling has enough function to maintain the fuel soundness keeping cladding temperature below the design criterion of 200 °C. The experiments will be continued to clarify transient thermal behaviors along with the development of an analysis code, and the designing work to get an efficient system for cooling fuel bundles will be also continued.
AB - The development of the fast reactor (FR) cycle is being preceded in Japan to utilize the plutonium and trans-uranium (TRU) efficiently. As the fuel generates heat due to decay of the TRU, it is required to develop an efficient system for cooling of the wire wrapped fuel pin bundle during the fabrication process where the bundle is being laid in horizontal state. To meet the requirement the four year study has started in 2006 sponsored by the Japanese government. In the first year the fabrications of the full mock-up and the enlarged- partial model were completed and the steady state heat removal tests have been performed. The temperature distribution data in the fuel bundle have been obtained and analyses have been also performed to compare with those measured data. The steady state experiments have revealed that the air cooling has enough function to maintain the fuel soundness keeping cladding temperature below the design criterion of 200 °C. The experiments will be continued to clarify transient thermal behaviors along with the development of an analysis code, and the designing work to get an efficient system for cooling fuel bundles will be also continued.
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M3 - Conference contribution
AN - SCOPUS:70349876708
SN - 9781605607870
T3 - International Conference on Advances in Nuclear Power Plants, ICAPP 2008
SP - 1899
EP - 1905
BT - American Nuclear Society - International Conference on Advances in Nuclear Power Plants, ICAPP 2008
T2 - International Conference on Advances in Nuclear Power Plants, ICAPP 2008
Y2 - 8 June 2008 through 12 June 2008
ER -