TY - JOUR
T1 - Critical Power Performance of the Tight-lattice Fuel Bundle
AU - Yamamoto, Yasushi
AU - Morooka, Shinichi
AU - Arai, Kenji
AU - Shirakawa, Kenetsu
PY - 2002
Y1 - 2002
N2 - Currently, a reactor core for boiling water reactors (BWRs) which improves a conversion ratio to about 1 is being examined. Since the gap between fuel rods must be narrowed to about 1.3 mm, it is expected that the fuel cooling performance would deteriorate. However, there are few thermal-hydraulic measurement data for tight lattice rod bundle. Therefore, the thermal-hydraulic tests using the tight lattice bundle were carried out under the BWR operating condition. As a result, the boiling transition behavior was similar to the liquid film dryout, which is the boiling transition mechanism of the conventional BWR fuel bundle. Moreover, the tendency of thermal-hydraulic performance for the flow condition parameters was the same as for the conventional BWR. Next, the applicability of the correlation developed by Arai et al. was examined to evaluate the critical power. These test data could be predicted accurately by Arai's correlation. Arai's correlation is based on the measurement data obtained by LeTouneau et al. Thus, Arai's correlation is expected to have wide applicability for various tight lattice bundles.
AB - Currently, a reactor core for boiling water reactors (BWRs) which improves a conversion ratio to about 1 is being examined. Since the gap between fuel rods must be narrowed to about 1.3 mm, it is expected that the fuel cooling performance would deteriorate. However, there are few thermal-hydraulic measurement data for tight lattice rod bundle. Therefore, the thermal-hydraulic tests using the tight lattice bundle were carried out under the BWR operating condition. As a result, the boiling transition behavior was similar to the liquid film dryout, which is the boiling transition mechanism of the conventional BWR fuel bundle. Moreover, the tendency of thermal-hydraulic performance for the flow condition parameters was the same as for the conventional BWR. Next, the applicability of the correlation developed by Arai et al. was examined to evaluate the critical power. These test data could be predicted accurately by Arai's correlation. Arai's correlation is based on the measurement data obtained by LeTouneau et al. Thus, Arai's correlation is expected to have wide applicability for various tight lattice bundles.
KW - BWR type reactors
KW - conversion ratio
KW - correlation
KW - critical power
KW - dryout
KW - thermal-hydraulic test
KW - tight lattice fuel bundle
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U2 - 10.3327/taesj2002.1.282
DO - 10.3327/taesj2002.1.282
M3 - Article
AN - SCOPUS:85010576026
VL - 1
SP - 282
EP - 288
JO - Transactions of the Atomic Energy Society of Japan
JF - Transactions of the Atomic Energy Society of Japan
SN - 1347-2879
IS - 3
ER -