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Journal Articles

ROSA-IV/LSTF experiment simulating loss-of-residual heat removal; Pressurization mechanism at experiment without opening

Nakamura, Hideo; Katayama, Jiro; Anoda, Yoshinari; Kukita, Yutaka

Nihon Kikai Gakkai Dai-69-Ki Tsujo Sokai Koenkai Koen Rombunshu, Vol.B, p.456 - 458, 1992/00

no abstracts in English

Oral presentation

Development of evaluation method for the non-condensable gas behavior in primary coolant system of sodium-cooled fast reactor; Effect of dipped-plate on bubble behavior in pool type reactor

Matsushita, Kentaro; Ezure, Toshiki; Tanaka, Masaaki; Ito, Kei*

no journal, , 

A numerical simulation code named SYRENA has been developed in Japan Atomic Energy Agency to analyze non-condensable gas behavior in primary coolant system. In this study, for a typical pool type reactor with a horizontal plate (dipped-plate:D/P) below the free surface of a hot plenum to suppress bubble entrainment into primary coolant system and to prevent fluctuation of free surface, non-condensable gas behavior in primary coolant system was evaluated with SYRENA. Parametric analyses was performed on sodium exchange flow rate through D/P and Ar bubble entrainment rate at free surface. It was clarified that effect on void fraction at core inlet by change of Ar bubble entrainment rate at free surface is greater than that by exchange flow rate through D/P. It was implied that suppressing Ar bubble entrainment at free surface by D/P suppressed increasing void fraction of the total bubbles in primary coolant system.

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