Flow channel selection method and system for rod bundle channel chf under the action of transient external force field
A rod bundle channel and external force technology, which is applied in the field of channel selection of rod bundle channel CHF under the action of a transient external force field, can solve problems such as changes in position and size, and the method for determining the channel is no longer applicable, and achieves good economy. , good consistency, strong achievable effect
Active Publication Date: 2022-02-11
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology
However, the position and size of CHF may change due to the action of the transient external force field. In order to better identify the influence of the transient external force field on CHF, the existing flow channel determination method under static conditions is no longer applicable.
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[0047] The flow channel selection method of the rod bundle channel CHF under the action of a transient external force field, such as figure 1 shown, including the following steps:
[0048] (1) Obtain the rod bundle channel scale;
[0049] First, sort out the parameters of the prototype large-scale fuel assembly to obtain the distribution of fuel rods in the prototype large-scale fuel assembly (N×N arrangement), the diameter of the fuel rods, the distance between adjacent fuel rods and the distance between the rods.
[0050] Among them, the prototype large-scale fuel assembly is composed of several typical bundle flow channels, such as figure 2 As shown, D is the diameter of the fuel rod, P is the distance between two adjacent fuel rods, and L is the distance between the rods.
[0051] Secondly, carry out the selection of the channel scale of the rod bundle. During the selection process, the diameter of the fuel rods, the distance between adjacent fuel rods and the distance ...
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The invention discloses a flow channel selection method and system for a rod bundle channel CHF under the action of a transient external force field. The method includes the following steps: obtaining the rod bundle channel scale; Select part of the fuel rods in the large-scale fuel assembly; obtain the optimal rod bundle channel scale, the optimal rod bundle channel scale is: the flow heat transfer characteristics of the rod bundle channel scale are the same as the flow heat transfer characteristics of the prototype large-scale fuel assembly and the fuel rods The smallest number of rod bundle channel scales; obtaining the optimal parameters of the optimal rod bundle channel scale, the optimal parameters are: the parameter values that make the average temperature and average flow velocity of each sub-channel in the optimal rod bundle channel scale relatively close. The object of the present invention is to provide a method and system for selecting the channel of the rod bundle channel CHF under the action of a transient external force field. According to the method or the system, the flow channel of the rod bundle body can be determined, and the transient external force field can be effectively identified for its CHF. The influence of characteristics.
Description
technical field [0001] The invention relates to the technical field of reactor thermal hydraulics, in particular to a flow channel selection method and system for a rod bundle channel CHF under the action of a transient external force field. Background technique [0002] The design and construction of new nuclear power devices such as offshore nuclear power floating platforms require experimental research on the core CHF (critical heat flux) to obtain the calculation formulas required for design. Bundle fuel assembly is a fuel assembly form commonly used in modern large pressurized water reactor cores, and its coolant flow channels are open channels communicating with each other. The transient external force field may significantly change the cross-flow characteristics between the channels, thereby significantly changing the local state parameters, resulting in changes in the position where the boiling criticality occurs in the component and the value of CHF. Therefore, the ...
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Login to View More IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 贺艳秋周磊黄彦平昝元锋岳倪娜
Owner NUCLEAR POWER INSTITUTE OF CHINA