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Apparatus for increasing the critical heat flux for high pressure steam/water flow in nuclear reactors

机译:用于增加核反应堆中高压蒸汽/水流的临界热通量的设备

摘要

1,061,878. Cooling reactors. ATOMIC ENERGY OF CANADA Ltd. Aug. 5, 1965 [Aug. 31, 1964], No. 33626/65. Heading G6C. In a nuclear reactor employing a mixture of steam and water as a coolant, turbulence is induced in the coolant to maintain efficient heat transfer between the fuel and coolant. The fuel, in rod form, is mounted vertically in pressure tubes down which the coolant is pumped under pressure. Circumferential rings are attached to the smooth inner surface of the pressure tubes. The rings deflect fluid from the pressure tube surface inwardly towards the fuel rods. The rings may have any cross-section but are spaced apart so as not to produce neutron absorption.
机译:1,061,878。冷却反应堆。加拿大原子能公司。1965年8月5日[八月。 1964年3月31日],编号33626/65。标题G6C。在采用蒸汽和水的混合物作为冷却剂的核反应堆中,在冷却剂中引起湍流,以保持燃料和冷却剂之间的有效传热。棒状燃料垂直安装在压力管中,冷却液在压力管中向下泵入。周向环连接到压力管的光滑内表面。环使流体从压力管表面向内朝燃料棒偏转。这些环可以具有任何横截面,但是间隔开以便不产生中子吸收。

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