Data Report of a tight-lattice rod bundle thermal-hydraulic tests, 1; Base case test using 37-rod bundle simulated water-cooled breeder reactor (Contract research)

Kureta, Masatoshi; Tamai, Hidesada; Liu, W.; Sato, Takashi; Watanabe, Hironori; Onuki, Akira; Akimoto, Hajime

JAEA-Data/Code 2006-007, 90 Pages, 2006/03

JAEA-Data-Code-2006-007.pdf:14.83MB

Japan Atomic Energy Agency has been performing tight-lattice rod bundle thermal-hydraulic tests as one of essential technologies for the technological and engineering feasibility of super high burn-up water-cooled breeder reactor which aims to achieve a high breeding ratio and super high burn-up by innovative performance-up of water-cooled reactor. The tests are performing to make clear the fundamental subjects related to the boiling transition(BT)(Subjects:BT criteria under a highly tight-lattice rod bundle, effects of gap-width between rods and of rod-bowing) using 37-rod bundles (Base case test section (1.3mm gap-width), Two parameter effect test sections (Gap-width effect one (1.0mm) and Rod-bowing one)). In the present report, we summarize the test results from the base case test section. The thermal-hydraulic characteristics using the large scale test section were obtained for the critical power, the pressure drop and the wall heat transfer under a wide range of pressure, flow rate, etc. including normal operational conditions of the designed reactor. Effects of local peaking factor on the critical power were also obtained.