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- W1570276402 abstract "Results of large-scale thermal-hydraulic test and model experiments which simulate the Reduced-Moderation Water Reactor (RMWR) core are summarized. Especially, rod number effect on critical power which was investigated using 7-rod and 37-rod bundle test result and void distribution which was measured by neutron tomography etc. are reported. (authors)" @default.
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- W1570276402 date "2004-07-01" @default.
- W1570276402 modified "2023-09-27" @default.
- W1570276402 title "Development of predictable technology for thermal/hydraulic performance of reduced-moderation water reactors (2) - Large-scale thermal/hydraulic test and model experiments" @default.
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