An Iterative Method for Core-Heat Coupling of Supercritical Water Reactor

A supercritical water reactor, nuclear thermal coupling technology, applied in special data processing applications, instruments, electrical digital data processing and other directions, can solve the problem of iterative calculation difficult to converge, to solve the iterative convergence problem, improve computational efficiency, ensure Effects of Numerical Stability

Active Publication Date: 2018-03-30
NUCLEAR POWER INSTITUTE OF CHINA
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  • Application Information

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Problems solved by technology

[0005] The purpose of the present invention is to overcome the shortcomings and deficiencies of the above-mentioned prior art, and provide a supercritical water reactor core thermal coupling iterative method, which solves the difficulty of iterative calculation in the supercritical water reactor core thermal coupling calculation process. Convergence issues, and improve the computational efficiency and numerical stability of nuclear thermal coupling calculations

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Embodiment 1

[0035] like figure 1 As shown, a supercritical water reactor core-nuclear thermal coupling iterative method includes the following steps S1-S7:

[0036] S1. Set the neutronics calculation iteration number m, construct the power density distribution iterative function; initialize and execute the neutronics calculation number n, and set the value of n to 0 when initializing n in this embodiment;

[0037] S2. Perform the first neutronics calculation, and jump to step S3 after counting the number of neutronics calculations; in this embodiment, the method of counting the number of neutronics calculations is: add 1 to the number of neutronics calculations, That is, the value of n+1 is assigned to n, and in this step, the value of n is 1 after the number of neutronics calculations is increased by 1;

[0038] S3. Using the power density distribution P obtained by performing the first neutronics calculation 1 Execute the second neutronics calculation, and count the number of neutroni...

Embodiment 2

[0064]In this embodiment, a supercritical water reactor core thermal coupling calculation method based on the iterative method in embodiment 1 or embodiment 2 is provided, such as figure 2 shown, including the following steps:

[0065] (1) Calculation of different fuel consumption conditions of components;

[0066] (2) Perform section fitting processing;

[0067] (3) Initial control rod position and water density distribution;

[0068] (4) Adjust the position of the control rod;

[0069] (5) Core-nuclear thermal coupling iterations until the power density distribution obtained after performing thermal-hydraulic calculations converges;

[0070] (6), judge whether to critical state, then jump to step (7), otherwise jump to step (4);

[0071] (7) Calculate the maximum cladding wall temperature according to the maximum power density distribution;

[0072] (8) Execute fuel consumption calculation;

[0073] (9) Determine whether the fuel has reached the end of its life, if so...

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Abstract

Supercritical water reactor core thermal coupling iterative method, after performing m times of neutronics calculations, perform a thermal hydraulic calculation, m is the set number of neutronics calculation iterations, m is greater than 5; when performing neutronics calculations In , the adaptive relaxation factor ω is introduced and the power density distribution obtained from the second to the mth execution of neutronics calculation is adjusted by using the power density distribution iterative function. The adjusted power density distribution is used for the next execution of neutronics calculation In or thermal hydraulic calculation. The invention solves the problem that iterative calculation is difficult to converge in SCWR nuclear thermal coupling calculation, and improves the calculation efficiency and numerical stability of nuclear thermal coupling calculation.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor design, in particular to an iterative method for core-nuclear thermal coupling of a supercritical water reactor. Background technique [0002] The operating condition of supercritical water reactor (SCWR) is above the thermodynamic critical point of water (374°C, 22.1MPa), which has high system thermal efficiency and the reactor system is simplified and compact. However, the density, specific heat and thermal conductivity of supercritical water change drastically in the supercritical region. The density of the agent is about 777kg / m at the core inlet 3 Change to about 90kg / m at core outlet 3 . The drastic change of water density significantly affects the neutron moderation capacity in the core, and the change of power density distribution caused by the change of moderation capacity will in turn significantly affect the distribution of water density in the core. This physical-thermal co...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F17/50
CPCG06F30/367G06F2119/06G06F2119/08Y02E60/00
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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