Device and method for simulating steam environment in containment in accident working condition of nuclear power plant
A technology of accident conditions and nuclear power plants, applied in nuclear engineering, nuclear power generation, nuclear reactor monitoring, etc., can solve problems such as the steam environment that has not yet been disclosed, and achieve the effects of low processing difficulty, wide application range, and flexible adjustment
Active Publication Date: 2018-12-14
XI AN JIAOTONG UNIV
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Problems solved by technology
[0003] Up to now, there has not been a publicly available device that can create a steam environment with a given pressure and a given helium quality to simulate the steam environment in the containment of a nuclear power plant accident.
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[0016] The present invention will be described in further detail below in conjunction with the accompanying drawings.
[0017] Such as figure 1 and figure 2 As shown, the present invention is a device for simulating the steam environment in the containment of a nuclear power plant accident, including a cylindrical pressure vessel 1, a compression pump 6, a helium source 7, a molecular vacuum pump 8, and the pipeline used for connection 9. It also includes a plurality of U-shaped tube heating rods 2 that are evenly arranged around the inner wall of the cylindrical pressure vessel 1 at the same height and one end is fixed on the inner wall of the cylindrical pressure vessel. The spaced U-shaped tube heating rods 2 are connected to a non-interval manual pressure regulator 5, and the remaining three-quarters of the adjacent U-shaped tube heating rods 2 are connected as a group to an on-off switch 4, Connect the U-shaped tube heating rod 2 to the multiple wires 3 on the on-off s...
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The invention discloses a device and method for simulating the steam environment in a containment in an accident working condition of a nuclear power plant. The device comprises a columnar pressure container, a compression pump, a helium source, a molecular vacuum pump and a pipeline for connection. The device also comprises a plurality of U-shaped tube heating rods which are uniformly arranged around the inner wall at the same height of the columnar pressure container tank and are fixed to the inner wall of the columnar pressure container tank at one ends. 1 / 4 U-shaped heating rods which areuniformly spaced are all communicated with a gapless manual pressure regulator and the adjacent U-shaped heating rods in the residual 3 / 4 U-shaped heating rods form a group communication to an on-offswitch to connect the U-shaped heating rods to a plurality of wires on the on-off switch or the gapless manual pressure regulator. The invention also discloses a method for simulating the steam environment in the containment in the accident working condition of the nuclear power plant. The device has the characteristics of being simple in structure, easy to process, wide in application range and high in reliability.
Description
technical field [0001] The invention belongs to the field of nuclear power plant accident simulation experiments, and in particular relates to a device and method for simulating the steam environment in a containment vessel under nuclear power plant accident conditions. Background technique [0002] At present, with the development of nuclear energy, nuclear safety has been widely concerned by the whole society. Special attention is paid to carrying out experiments for the safety analysis of nuclear reactors, among which the simulation of the vapor space under containment accident conditions is becoming more and more common. A large amount of hydrogen and steam may be produced in the containment of a nuclear power plant in an accident state, so that all the equipment in the containment are in such an environment. Therefore, we need to design a condensation space with wide application range and high reliability, which can simulate the mixture of hydrogen and steam under the ...
Claims
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Login to View More IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 陈荣华张鹏辉马攀田文喜秋穗正苏光辉
Owner XI AN JIAOTONG UNIV