THERMO-HYDRAULIC MODEL TEST OF THE FIRST NUCLEAR SHIP REACTOR IN JAPAN(Collected Papers Published by Staff of Ship Research Institute at societies and Institutions in 1969)

概要

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A series of thermo-hydraulic model tests were carried out to confirm that the first nuclear ship reactor in Japan was properly designed. The major test models were a half-size core structural model, a full-size fuel assembly model and a half-size steam generator plenum model.The measured results were compared with the design calculation of the reactor. Most of the calculated results were found to be in good agreement with experiment. However, the pressure drop in the reactor vessel was found to be overestimated, and a necessary correction was made on the system design. Also flow velocity distribution was found to be much more distorted than expected in the fuel assembly, and an appropriate design modification was made in the lower end plate.Flow coastdown in the primary loop and coolant mixing in the fuel assembly are also discussed.
独立行政法人海上技術安全研究所の論文
1970-03-01