Universal sodium-cooled fast reactor assembly single-body hydraulic experiment bench and experiment method thereof

A technology for sodium-cooled fast reactors and hydraulic experiments, which is used in reactors, nuclear reactor monitoring, and greenhouse gas reduction. It can solve problems such as poor scalability, less flow characteristics of all components, and lack of experimental research. Effect

Pending Publication Date: 2019-07-19
NORTH CHINA ELECTRIC POWER UNIV (BAODING)
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  • Abstract
  • Description
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  • Application Information

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Problems solved by technology

[0004] (1) Most of the research methods are numerical simulation methods, but there is a lack of relevant experimental research;
[0005] (2) Most of the experimental studies carried out focused on the flow characteristics of the tape-wound r...

Method used

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  • Universal sodium-cooled fast reactor assembly single-body hydraulic experiment bench and experiment method thereof
  • Universal sodium-cooled fast reactor assembly single-body hydraulic experiment bench and experiment method thereof
  • Universal sodium-cooled fast reactor assembly single-body hydraulic experiment bench and experiment method thereof

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Embodiment Construction

[0032] The embodiments will be described in detail below in conjunction with the accompanying drawings.

[0033] The experimental platform of the present invention is composed of a water purification system, a voltage stabilizing system, a main circulation system and an experimental section. The purification system includes deionized water equipment and a feed water pump. Due to the fine structure of the simulated components used in the experimental section, if there are large impurities in the experimental working fluid, it is easy to cause surface scaling or even impurity accumulation to block the flow channel. Therefore, The experiment uses deionized water equipment to prepare deionized water, and its conductivity is less than 0.5μs / cm, which meets the water quality requirements of the experiment, thus ensuring the reliability of the flow condition from the source and also conducive to the accuracy of the measurement; the voltage stabilization system mainly includes high Th...

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Abstract

The invention belongs to the technical field of flow characteristic experiments of sodium-cooled fast reactor assemblies, and particularly relates to a universal sodium-cooled fast reactor assembly single-body hydraulic experiment bench and an experiment method thereof. The experiment bench comprises a water purification system, a pressure stabilizing system, a main circulation loop and an experiment section which are sequentially connected, wherein a heating section in the main circulation loop and the experiment section are connected in parallel; and a measured experiment simulation piece isplaced in the experiment section. The experimental method comprises the following steps: injecting deionized water into the main circulation loop and the experimental section, and discharging gas gathered in a pipeline; starting a water feeding pump of a main circulation system, and establishing stable circulation flow in an experiment loop; heating an experiment working medium to a preset temperature, and then closing a heater; and adjusting the frequency of a main water feeding pump and the opening degree of an outlet valve to achieve switching of different experiment working conditions, and collecting and recording experiment data. The flow characteristics of various assemblies and corresponding rod bundle sections of a sodium-cooled fast reactor can be studied through hydraulic experiments, and the sodium-cooled fast reactor assembly single-body hydraulic experiment bench has high universality and expansibility.

Description

technical field [0001] The invention belongs to the technical field of flow characteristic experiments of sodium-cooled fast reactor components, and in particular relates to a general-purpose sodium-cooled fast reactor component hydraulic test bench and an experimental method thereof. Background technique [0002] The sodium-cooled fast reactor is a new generation of nuclear power reactor. The relevant functional components in the core are distributed in different positions and structures, and the corresponding flow characteristics are also quite different. Through reasonable structural design, the components can meet the expected performance requirements. Due to the extremely complex internal structure of the components, the flow state of the coolant is extremely complex and tortuous, and it is impossible to accurately obtain the flow characteristics of the components using theoretical methods such as computational fluid dynamics, and the flow characteristics of the componen...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 陆道纲秦亥琦钟达文司宇刘少华
Owner NORTH CHINA ELECTRIC POWER UNIV (BAODING)
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