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Improvements in or relating to methods of testing applicable to the control of nuclear reactors

机译:适用于核反应堆控制的测试方法的改进或与之相关的改进

摘要

917,937. Nuclear reactors. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. Dec. 1, 1961 [Dec. 9, 1960], No. 42394/60. Drawings to Specification. Class 39 (4). A method of testing fuel elements in a nuclear reactor comprises rapidly raising the temperature of fuel elements in a coolant channel while the reactor is operating at power so that a transient burst of fission products is emitted from any existing leaks in the fuel element sheaths into the coolant stream for detection by monitoring apparatus. The rate of increase of temperature should be at least 4 ‹ C./minute, the difference between the initial and final temperatures at least 4‹ C., and the final temperature at least 400‹ C. The temperature may be increased by reducing the coolant flow while the coolant pressure remains unaltered or by increasing the reactor power. Another method comprises increasing the coolant flow by increasing the speed of the coolant blowers, thus causing an initial drop in temperature, and then increasing the power of the reactor to restore the fuel elements to their initial temperature. Specification 897,450 is referred to.
机译:917,937。核反应堆。联合王国原子能机构。 1961年12月1日[12月1960年9月],编号42394/60。图纸按规格。 39类(4)。一种用于测试核反应堆中燃料元件的方法,该方法包括在反应堆以功率运行时迅速提高冷却剂通道中燃料元件的温度,以便使裂变产物的瞬变爆发从燃料元件护套中的任何现有泄漏物散发出来。冷却液流,供监控设备检测。温度的升高速率应至少为4°C /分钟,初始和最终温度之间的差至少为4°C,最终温度至少为400°C。可以通过降低温度来提高温度。当冷却剂压力保持不变或通过增加反应堆功率时,冷却剂流动。另一种方法包括通过增加冷却剂鼓风机的速度来增加冷却剂流量,从而引起温度的初始下降,然后增加反应堆的功率以将燃料元件恢复到其初始温度。参考规范897,450。

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