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High-power thick rod fuel element simulation device

A fuel element and simulation device technology, applied in nuclear reactor monitoring, reactors, nuclear power generation, etc., can solve the problems that simulation components are not suitable for pool reactor fuel element simulation devices, so as to alleviate flow instability, volume increase, prevent burnt effect

Active Publication Date: 2020-05-15
NORTHWEST INST OF NUCLEAR TECH
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] In order to solve the problem that the existing simulation components are not suitable as a simulation device for pool reactor fuel elements, the present invention provides a high-power thick rod fuel element simulation device

Method used

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  • High-power thick rod fuel element simulation device

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Embodiment Construction

[0041] The present invention will be further described below in conjunction with the accompanying drawings and specific embodiments.

[0042] The core heat source is to generate energy through the fission of nuclear fuel. Usually, the critical heat flux experiment uses electric heating to simulate the heating of the fuel element, and the size of the heating part of the simulated element should be consistent with the size of the heating part of the pool reactor fuel element.

[0043] The experimental working conditions must be consistent with the operating conditions of the pool reactor, that is, to meet the requirements of natural circulation, and the core inlet pressure is 0.16MPa. In order to meet the requirements of the critical heat flux experiment, the power of the simulation device must reach a predetermined value, and the size and characteristics of the selected simulation components must be determined according to the power requirements.

[0044] In the critical heat ...

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Abstract

The invention relates to a high-power thick rod fuel element simulation device. The device comprises a heating assembly and a cylinder body; the heating assembly is sleeved in the cylinder body, and amedium circulation channel is formed between the heating assembly and the cylinder body; and the heating assembly comprises a heat conduction core rod, a screw plug, an outer conductive tube, a ceramic inner tube, a ceramic outer tube, a connecting tube and a positioning head. By reasonably arranging the interface positions of a thermocouple, a pressure gauge and a differential pressure gauge andarranging a heating section and a non-heating section in the heat conduction core rod, the operation condition of a pool type research reactor is met, high-power stable operation can be achieved, andresearch on the critical heat flux density of the pool type research reactor is achieved.

Description

technical field [0001] The invention belongs to the research field of thermal hydraulic experiments, and in particular relates to a high-power thick rod fuel element simulation device. Background technique [0002] The critical heat flux phenomenon on the surface of fuel element cladding is not allowed in the reactor thermal safety design criteria. Therefore, it is necessary to carry out experimental research on critical heat flux in reactor design to obtain the magnitude of critical heat flux under different operating conditions to ensure the thermal safety performance of the reactor. [0003] The fuel element core of the pool reactor is arranged in an equilateral triangle, with 9 circles and a total of 211 holes, of which, standard fuel elements occupy 99 holes, the diameter of the fuel element is 37.2mm, and the length of the fuel segment is 0.39mm. The structural size of the fuel element is similar to that of conventional PWR fuel rod elements vary widely in size. [0...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 陈森杨宁李华琪朱磊康小亚田晓艳陈立新
Owner NORTHWEST INST OF NUCLEAR TECH
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