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Core thermohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3
Core thermohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3,10.3327/jnst.22.551,Journal of Nuclear Science and Technology,Yukio
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Core thermohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3
(
Citations: 2
)
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Yukio SUDO
,
Hiroei ANDO
,
Hiromasa IKAWA
,
Nobuaki OHNISHI
Journal:
Journal of Nuclear Science and Technology - J NUCL SCI TECHNOL
, vol. 22, no. 7, pp. 551-564, 1985
DOI:
10.3327/jnst.22.551
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Citations
(2)
Development of a steady thermal-hydraulic analysis code for the China Advanced Research Reactor
(
Citations: 2
)
Wenxi Tian
,
Suizheng Qiu
,
Yun Guo
,
Guanghui Su
,
Dounan Jia
,
Tiancai Liu
,
Jianwei Zhang
Journal:
Frontiers of Energy and Power Engineering in China
, vol. 1, no. 2, pp. 189-194, 2007
Improvement of Critical Heat Flux Correlation for Research Reactors using Plate-Type Fuel
Masanori KAMINAGA
,
Kazuyoshi YAMAMOTO
,
Yukio SUDO
Journal:
Journal of Nuclear Science and Technology - J NUCL SCI TECHNOL
, vol. 35, no. 12, pp. 943-951, 1998