抄録
We studied on the mock-up flow test of the natural uranium, heavy water cooled and moderated research reactor named JRR-3, 10 MW in thermal power. This mock-up test equipment is constructed with the main loop of heavy water flow, containing a mock-up core tank, a circulating pump, a flow control system and a water level regulating system.
This report presents data on the following tests:
(1) the flow resistance of the model fuel element
(2) the vibration of the model fuel element by flow
(3) the leakage through the contact part between the model fuel element and its seat
(4) the flow distribution of the fuel elements from the lower plenum of the core tank
(5) the flow characteristics of the total system on the effect of the flow control mechanism
(6) the flow of the model fuel element when the clearance between the fuel element and its seat was changed
