稠密37本バンドル熱特性試験と熱流動モデル実験(NP3 新型炉技術)

概要

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Main purposes of the tight-lattice 37-rod bundle thermal-hydraulic tests (37-rod tests) and model experiments are to investigate the scale effect (rod-number effect) on critical power and to obtain the detailed thermal-hydraulic data for understanding the phenomena and estimating the advanced numerical analysis codes, respectively. The 37-rod bundle test section and some test sections for the model experiments simulate the Reduced-Moderation Water. Reactor core. It was found from the comparison of 37-rod test data with existing 7-rod test data that critical quality increase with increasing the rod number. Using the spacer-effect fundamental neutron radiography experiment, void fraction distribution around the object, which simulates the spacer, in a heated tube was discussed. From the 14-rod bundle neutron 3D tomography experiments, it was found that vapor tends to move the center region of the flow channel.
社団法人日本機械学会の論文
2004-06-22