Low-voltage high-power pressurized water reactor fuel assembly simulation device

A fuel assembly and simulation device technology, which is applied in the simulation process of specific applications, reactors, nuclear power generation, etc., can solve the problems of large energy consumption and complex structure of the device, and achieve the effect of reducing loss and cost and facilitating replacement
CN107799192AActive Publication Date: 2018-03-13NUCLEAR POWER INSTITUTE OF CHINA
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Patent Information

Authority / Receiving Office
CN ยท China
Current Assignee / Owner
NUCLEAR POWER INSTITUTE OF CHINA
Publication Date
2018-03-13

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Abstract

The invention discloses a low-voltage high-power pressurized water reactor fuel assembly simulation device, which comprises a pressure-bearing assembly, an electric heating assembly and a square flowchannel, wherein the square flow channel is arranged in the pressure-bearing assembly and is hermetically connected with the pressure-bearing assembly; and the electric heating assembly simultaneouslypasses through the square flow channel and the pressure-bearing assembly and is sealed with and fixed to the pressure-bearing assembly. The device meets requirements of a high-temperature and high-pressure experiment, keeps thermal hydraulic characteristic similarity with a reactor fuel assembly, can realize a simulation process of a low-voltage high-power pressurized water reactor fuel assembly,has low energy consumption, simplifies the structure, and is used for the critical heat flux and flow instability experiments of the pressurized water reactor fuel assembly so as to verify the thermal safety performance of a reactor.
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Description

technical field

[0001] The invention relates to a pressurized water reactor rod bundle fuel assembly simulation device, in particular to a low voltage and high power pressurized water reactor fuel assembly simulation device. Background technique

[0002] A number of steady-state thermal design criteria are specified in the reactor design, including that the outer wall of the fuel element does not allow boiling criticality; in the steady-state rated conditions and expected transient operating conditions, no flow instability occurs . Therefore, in reactor design, critical heat flux and flow instability experiments need to be carried out to obtain critical heat flux values โ€‹โ€‹and stable operating boundaries under different operating conditions to verify the thermal safety performance of the reactor.

[0003] PWR fuel assemblies are generally composed of fuel rods with a diameter of 10mm arranged in a square of 15ร—15 or 17ร—17. The heat source is the energy generated by the fissi...

Claims

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