TY - JOUR
T1 - Proving test on thermal-hydraulic performance of bwr fuel assemblies
AU - Tsukuda, Yoshiaki
AU - Hayashi, Hiroshi
AU - Kamimura, Katsuichiro
AU - Hattori, Toshiitsu
AU - Kaneko, Hirohisa
AU - Morooka, Shinichi
AU - Mitsutake, Torn
AU - Akiba, Miyuki
AU - Abe, Nobuaki
AU - Warashina, Masahiko
AU - Masuhara, Yasuhiro
AU - Kimura, Jiro
AU - Tanabe, Akira
AU - Nishino, Yuji
AU - Isaka, Koujun
AU - Suzuki, Riichiro
PY - 2002
Y1 - 2002
N2 - Nuclear Power Engineering Corporation (NUPEC) has conducted a proving test for thermal-hydraulic performance of BWR fuel (high-burnup 8×8, 9×9) assemblies entrusted by the Ministry of Economy, Trade and Industry (NUPEC-TH-B Project). The high-burnup 8×8 fuel (average fuel assembly discharge burnup: about 39.5GWd/t), has been utilized from 1991. And the 9 × 9 fuel (average fuel assembly discharge burnup: about 45GWd/t). has started to be used since 1999. There are two types (A-type and B-type) of fuel design in 9×9 fuel assembly. Using an electrically heated test assembly which simulated a BWR fuel bundle on full scale, flow induced vibration, pressure drop, critical power under steady state condition and post-boiling transition (post-BT) tests were carried out in an out-of pile test facility that can simulate the high pressure and high temperature conditions of BWRs. This paper completed the results of 9 × 9 fuel combined with the previously reported results of high-burnup 8×8 fuel. As a result of NUPEC-TH-B Project, the validity of the current BWR thermal-hydraulic design method was confirmed and the reliability of BWR thermo-hydraulic fuel performance was demonstrated. Based on the test data, a new correlation of the estimation of fuel rod vibration amplitude, new post-BT heat transfer and rewet correlations for the estimation of fuel rod surface temperature were developed.
AB - Nuclear Power Engineering Corporation (NUPEC) has conducted a proving test for thermal-hydraulic performance of BWR fuel (high-burnup 8×8, 9×9) assemblies entrusted by the Ministry of Economy, Trade and Industry (NUPEC-TH-B Project). The high-burnup 8×8 fuel (average fuel assembly discharge burnup: about 39.5GWd/t), has been utilized from 1991. And the 9 × 9 fuel (average fuel assembly discharge burnup: about 45GWd/t). has started to be used since 1999. There are two types (A-type and B-type) of fuel design in 9×9 fuel assembly. Using an electrically heated test assembly which simulated a BWR fuel bundle on full scale, flow induced vibration, pressure drop, critical power under steady state condition and post-boiling transition (post-BT) tests were carried out in an out-of pile test facility that can simulate the high pressure and high temperature conditions of BWRs. This paper completed the results of 9 × 9 fuel combined with the previously reported results of high-burnup 8×8 fuel. As a result of NUPEC-TH-B Project, the validity of the current BWR thermal-hydraulic design method was confirmed and the reliability of BWR thermo-hydraulic fuel performance was demonstrated. Based on the test data, a new correlation of the estimation of fuel rod vibration amplitude, new post-BT heat transfer and rewet correlations for the estimation of fuel rod surface temperature were developed.
KW - BWR type reactors
KW - correlation
KW - critical power
KW - flow induced vibration
KW - heat transfer
KW - post-BT
KW - pressure drop
KW - reliability
KW - rewet
KW - thermal-hydraulic performance
KW - vibration amplitude
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U2 - 10.3327/taesj2002.1.384
DO - 10.3327/taesj2002.1.384
M3 - Article
AN - SCOPUS:84930708063
SN - 1347-2879
VL - 1
SP - 384
EP - 403
JO - Transactions of the Atomic Energy Society of Japan
JF - Transactions of the Atomic Energy Society of Japan
IS - 4
ER -