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核动力装置要点,考点(Main points of nuclear power plant)
核动力装置要点,考点(Main points of nuclear power plant)
First, the noun explanation
The ratio of the critical heat flux predicted by DNBR to the actual heat flux at the surface of the fuel element is calculated by using a special formula according to the coolant state around the fuel element in the pile
Partition loading along the radial direction of the core is divided into three zones with different concentrations of fuel allocation has the highest concentration of fuel fuel element loading the region has the lowest concentration in the center zone and the middle zone of fuel concentration degree between the outer and central area between.
The true steam content is defined as the actual steam content of any cross section of the flow channel x, which is defined as the mass flow rate of the steam / the total mass flow of the liquid vapor mixture.
In the lower section of the driving pressure head, the negative value of the elevation pressure drop produced by single-phase water is equal to that of the ascending phase pressure drop of the rising water mixture.
The rate of emptying of an arbitrary flow system depends on the rate at which the fluid flows out of the exit or breach, i.e. mass flow. This flow is called critical flow when the rate at which fluid flows out of the system is no longer affected by downstream pressure drops.
A fuel coolant passage with maximum enthalpy rise in a heat pipe core
The ratio of maximum heat flux to core mean heat flux of heat flow hot spot factor core
The average tube is a hypothetical channel with a nominal size, average coolant flow rate, and average heat release rate. The mean tube reflects the mean characteristics of the entire core.
The critical heat flux just reached the boiling critical heat flux density
The ratio of the volume of steam to the total volume of a liquid mixture in the considered section
The effective pressure head usually refers to the residual drive head that overcomes the pressure loss at the rising section and is refer
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