Rod-shaped fuel element transient heat release simulation experiment device and method
A technology for fuel elements and simulation experiments, which is used in measuring devices, testing of machine/structural components, instruments, etc., to achieve the effects of low cost, good practicability and high precision
Active Publication Date: 2021-02-05
WUHAN SECOND SHIP DESIGN & RES INST
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[0006]
Aiming at the defects existing in the prior art, the object of the present invention is to provide a rod-shaped fuel element transient heat release simulation experiment device and method, which solves the problem that in the prior art it is difficult to reflect the heat transient in the fuel rod during the electric heating process outside the reactor. The problem of state release process
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[0042] The present invention will be described in further detail below in conjunction with the accompanying drawings and embodiments.
[0043] see Figure 1-3 As shown, the embodiment of the present invention provides a rod-shaped fuel element transient heat release simulation experiment device, which includes:
[0044] A fuel rod, comprising a pellet and a cladding surrounding the pellet, with an air gap evenly spaced between the pellet and the cladding; a coolant flow channel connecting at least two fuel rods A rod forming a closed annular channel structure is arranged outside the cladding of the fuel rod.
[0045] In a preferred embodiment, the fuel rods are arranged in a matrix, and the cross section of the coolant channel is a rectangle with the center of each fuel rod cross section as the vertex. like figure 2 It is the arrangement structure of the relative positions of the flow channels and the fuel rods in one embodiment. The fuel rods are arranged in a matrix, and...
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The invention discloses a rod-shaped fuel element transient heat release simulation experiment device and method, and relates to the field of nuclear reactor thermotechnical hydraulics. The rod-shapedfuel element transient heat release simulation experiment method comprises the steps of: S1, constructing a rod-shaped fuel element heat release structure which comprises a core block, a cladding arranged outside the core block, and a coolant flow channel located outside the cladding, wherein an air gap is reserved between the pellet and the cladding; S2, calculating time constants of a fuel rodand an electric heating element, and calculating the real-time thermal power according to the nuclear power of a reactor core; and S3, outputting electric power with the corresponding magnitude to anelectric heating circular pipe by means of a power supply control system in real time, and carrying out experimental simulation on the transient heat release condition of the rod-like fuel element ina reactor by means of the electric heating circular pipe. According to the rod-shaped fuel element transient heat release simulation experiment device and the rod-shaped fuel element transient heat release simulation experiment method, the problem that the transient heat release process in a fuel rod in the external heating process of a reactor is difficult to reflect in the prior art is solved.
Description
technical field [0001] The invention relates to the technical field of thermal hydraulics of nuclear reactors, in particular to a device and method for simulating transient heat release of rod-shaped fuel elements. Background technique [0002] The energy in a nuclear reactor mainly comes from the heat energy generated by fission in nuclear fuel rods. The fuel rods form a nuclear fuel assembly in a certain number and arrangement. The coolant flows between the fuel rods and brings heat to the steam generator. The steam generated drives the steam turbine. Work is done, converting thermal energy into mechanical energy. During the design process of nuclear fuel assemblies, it is necessary to conduct experimental research on the flow and heat transfer characteristics in the channels of rod-shaped fuel assemblies, but the heat release experiments of fuel rods cannot be carried out outside the reactor. [0003] The heat release process of the fuel rods in the reactor is generally ...
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IPC IPC(8): G01M99/00
CPCG01M99/002Y02E30/30
Inventor 陈先兵朱东保龙成毅郭洪婧陈景明孟海波刘少有邵燕
Owner WUHAN SECOND SHIP DESIGN & RES INST