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A heating device, nuclear reactor core power simulation device and method

A core power and nuclear reactor technology, applied in the field of simulation devices, can solve problems such as uneven distribution of nuclear reactor core power

Active Publication Date: 2019-04-30
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] The existing core power simulation methods all use uniform distribution simulation. In order to improve the simulation accuracy of nuclear reactor core thermal hydraulic experiments, it is very necessary to invent an experimental system and method that truly simulates the uneven distribution of nuclear reactor core power.

Method used

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  • A heating device, nuclear reactor core power simulation device and method
  • A heating device, nuclear reactor core power simulation device and method
  • A heating device, nuclear reactor core power simulation device and method

Examples

Experimental program
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Effect test

Embodiment 1

[0045] Such as Figure 1 to Figure 3 As shown, a heating device includes an electric heating element 2, and the electric heating element 2 includes an element a and an element b, and both the element a and the element b include an electric heating wire 6, and the electric heating wire 6 is strip-shaped , one end of the electric heating wire 6 is a terminal, and the terminals of each electric heating wire 6 are connected with two wires 9 for feeding current to each electric heating wire 6;

[0046] In the element a, along the length direction of the element a, from the terminal of the element a to the other end, the heating power of each point of the electric heating wire 6 increases monotonically and then decreases monotonically, and the maximum point of the heating power of the element a is close to The terminal of the electric heating wire 6;

[0047] In the element b, along the length direction of the element b, from the terminal of the element b to the other end, the heat...

Embodiment 2

[0059] The present embodiment is further limited on the basis of embodiment 1, as Figure 1 to Figure 3 As shown, as a further technical solution of the above heating device: as a specific implementation form of the electric heating wire 6, the electric heating wire 6 is in a U-shaped structure, and the terminal of the electric heating wire 6 is the open end of the U-shaped structure. Each end of the opening end of each electric heating wire 6 is connected with a wire 9, and in each electric heating wire 6, from the bottom end of the electric heating wire 6 to the opening end, the cross-sectional area of ​​the electric heating wire 6 first monotonically decreases and then monotonically increment. In the above structure, the length direction corresponding to the electric heating element 2 is from the bottom end of the electric heating wire 6 to the opening end. The electric heating wire 6 in this way is easy to manufacture. The heating power of the point changes smoothly, whic...

Embodiment 3

[0063] This embodiment further limits this case on the basis of the technical solution provided in embodiment 1: as Figure 1 to Figure 3 , as a further technical solution of the nuclear reactor core power simulation device described above, the fixing device 4 is a bolt threaded on each cladding 3, and the bolt provides compressive stress to the element a or element b, The fixation of element a or element b in the corresponding enclosure 3 is completed. In this solution, it is set that the fixing device 4 is a bolt, which not only makes the implementation of the fixing device 4 simple, but also facilitates the adjustment of the position of the components in the corresponding casing 3 . As a person skilled in the art, when the above bolts are threaded on the wall of the cladding 3, and the two sides of the element a or element b in the cladding 3 are respectively constrained by the inner wall of the cladding 3 and the compressive stress at the end of the bolt, the element a can...

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Abstract

The invention discloses a heating device, a nuclear reactor core power simulation device and a method. In the corresponding device and method, by manufacturing non-uniform electric heating elements that can match different axial power distributions of nuclear reactor core fuel elements at the beginning and end of their service life, Inserting two types of non-uniform electric heating elements directly into the cladding tube can simulate the axial non-uniform distribution of core power in the early and late stages of nuclear reactor life; by combining two types of non-uniform electric heating elements, and by electric The heating element position fixing and adjusting device controls the insertion depth of the non-uniform electric heating element, so that the core power axial non-uniform distribution simulation of the nuclear reactor in different periods can be realized. The device and method are simple and feasible, and can accurately accurately distribute the axial and radial non-uniform distribution of nuclear reactor core power under different service life periods.

Description

technical field [0001] The invention relates to the technical field of a simulation device for simulating the working state of a nuclear reactor, in particular to a heating device, a nuclear reactor core power simulation device and a method. Background technique [0002] In the research of nuclear reactor thermohydraulic experiments, it is necessary to simulate the power of the core under normal operating conditions and accident conditions, and to study the flow, heat transfer, critical heat flux and core fluid flow under normal operating conditions and accident conditions. Thermal hydraulic characteristics such as fuel element safety. Therefore, the simulation accuracy of core fuel elements directly affects the results of nuclear reactor core thermal-hydraulic experiments. [0003] The existing core power simulation methods all use uniform distribution simulation. In order to improve the simulation accuracy of nuclear reactor core thermal hydraulic experiments, it is very ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): H05B3/00G21C17/00
CPCG21C17/001H05B3/00Y02E30/30
Inventor 彭传新昝元锋白雪松张妍卓文彬闫晓
Owner NUCLEAR POWER INSTITUTE OF CHINA
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