2237 高稠密格子水冷却炉心の除熱技術の開発 (2) : 大型熱特性試験とモデル実験

概要

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In this manuscript, the key point of large-scale thermal-hydraulic tests and model experiments which simulate the Reduced-Moderation Water Reactor (RMWR) core are reported. The aim of the large-scale thermal-hydraulic tests using 37-rod bundle test facility is to make clear the rod number effect, rod gap effect etc. for investigating the feasibility of RMWR. Thermal-hydraulic model experiments will be performed in order to verify an advanced 3-D two-phase flow simulation method. Void fraction distribution and its fluctuation and basic thermal characteristics in tight lattice rod bundles will be measured by high-frame-rate neutron radiography technique etc. We will develop the database by 2007 that can resolve the fundamental feasibility subjects for the RMWR.
社団法人日本機械学会の論文
2003-08-05