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A 3D Transient Performance Analysis Method for Supercritical Water Reactor Core

A supercritical water reactor, three-dimensional transient technology, used in special data processing applications, instruments, electrical digital data processing, etc. , the effect of accurately estimating the safety margin and improving the core performance

Active Publication Date: 2018-09-11
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0007] The invention provides a three-dimensional transient performance analysis method for supercritical water reactor core, which solves the problem that the existing supercritical water reactor power distribution transient analysis method does not have the ability to calculate three-dimensional power coupled with core core heat, and it is difficult to real or Accurately simulate the technical problems of transient processes such as reactivity and abnormal power distribution events, realize the accurate description of the feedback between physics and thermal-hydraulic, provide more accurate three-dimensional power distribution of the core, and truly simulate supercritical Transient Process of Water Reactor and Technical Effect of Accident Process

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  • A 3D Transient Performance Analysis Method for Supercritical Water Reactor Core
  • A 3D Transient Performance Analysis Method for Supercritical Water Reactor Core
  • A 3D Transient Performance Analysis Method for Supercritical Water Reactor Core

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Embodiment 1

[0046] In the first embodiment, a 3D transient performance analysis method of supercritical water reactor core is provided, please refer to Figure 1-Figure 4 , the method includes:

[0047] Step 1: The three-dimensional steady-state physics-thermal-hydraulic coupling module of the supercritical water reactor core performs core steady-state calculations, the core fuel management module provides power parameters to the sub-channel thermal-hydraulic module, and the sub-channel thermal-hydraulic module Provide thermal parameters to the core fuel management module, and perform iterative coupling calculations until the core steady-state power parameters and thermal parameters converge;

[0048] Step 2: The three-dimensional steady-state physics-thermal-hydraulic coupling module of the core provides the core initial state and component section library to the three-dimensional transient physics-thermal-hydraulic coupling module of the supercritical water reactor core;

[0049] Step ...

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Abstract

The invention discloses a three-dimensional transient performance analysis method of a supercritical water reactor core, which includes: step 1: performing core steady-state calculation, providing power parameters and thermal parameters, performing iterative coupling calculation until the core steady-state power parameters and Convergence of thermal parameters; Step 2: Provide core initial state and component section library; Step 3: Perform transient calculation, provide power parameters and thermal parameters, perform iterative coupling calculation until core transient power parameters and thermal parameters converge ; Step 4: Get the fine power distribution of the cell scale of the thermal component, analyze the sub-channels of the thermal component, and finally give the key parameters of the safety evaluation; Step 5: Determine whether the key parameters of the safety evaluation exceed the corresponding transient or accident safety limits value, which can accurately describe the feedback between physics and thermal-hydraulic, provide a more accurate three-dimensional power distribution of the core, and truly simulate the technical effects of the transient process and accident process of supercritical water reactors.

Description

technical field [0001] The invention relates to the field of nuclear reactor design research, in particular to a three-dimensional transient performance analysis method for a supercritical water reactor core. Background technique [0002] The operating condition of the supercritical water reactor (SCWR) is above the thermodynamic critical point of water (374°C, 22.1MPa), the thermal efficiency of the system is high, and the economy is good, but at the same time, compared with the conventional water-cooled reactor, the operating parameters of the supercritical water reactor The core structure and coolant flow are relatively complex, which brings a lot of technical problems such as core physics, thermal-hydraulic and safety analysis. Among them, the strong nuclear thermal coupling characteristic is the core design and core of supercritical water reactor. One of the key technical problems of performance analysis. [0003] Among the abnormal reactivity events of supercritical w...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F19/00
CPCG16Z99/00
Inventor 王连杰赵文博卢迪陈炳德姚栋夏榜样于颖锐李庆
Owner NUCLEAR POWER INSTITUTE OF CHINA
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