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Control method and system of high temperature gas cooled reactor power

A high-temperature gas-cooled reactor and power control technology, which is applied in the field of nuclear energy science and engineering, and can solve problems such as the contradiction between the form and performance of the power control method of the high-temperature gas-cooled reactor.

Active Publication Date: 2014-04-02
CHINERGY CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] The technical problem to be solved by the present invention is: how to solve the problem of the contradiction between the form and performance of the high temperature gas-cooled reactor power control method

Method used

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  • Control method and system of high temperature gas cooled reactor power
  • Control method and system of high temperature gas cooled reactor power
  • Control method and system of high temperature gas cooled reactor power

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Experimental program
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Embodiment 1

[0134] The specific implementation of the parameter setting in the high temperature gas-cooled reactor power control method proposed by the present invention can refer to image 3 The flow chart is given, and the specific steps are as follows: the first step is to select its parameter σ according to the physical meaning of the transition process index function 1 , σ 2 and θ; in the second step, the physical parameters of the reactor are given, namely the delayed neutron share β, neutron generation time Λ and control rod differential value G r The value of ; the third step is to calculate the index function parameter σ according to the first inequality in equations (15) and (17) 1 and σ 2 The value range of ; the fourth step is to judge the selected σ 1 , σ 2 and θ meet the value range of the index function parameters, if not, reselect σ 1 , σ 2 and θ, otherwise, continue the design process; the fifth step, select the feedback coefficient F 1 and F 2 The value of ; sixth,...

specific example

[0136] The first step is to select the parameters of the transition process index function to satisfy σ 1 =0.2, σ 2 =0.1 and θ=0.1.

[0137] The second step, given the physical parameters of a certain high-temperature gas-cooled reactor: delayed neutron share β=0.005, neutron generation time Λ=0.001 second and control rod differential value G r = 0.001.

[0138] In the third step, according to the first inequality in equations (15) and (17), σ 1 and σ 2 The range of values ​​is

[0139] 0i <10, i=1, 2

[0140] The fourth step, according to the results of the first step and the third step, it can be judged that the parameter value selection of the transition process index function meets the requirements, and the design process continues.

[0141] The fifth step, choose to set the feedback coefficient F 1 =0.004, F 2 = 0.002.

[0142] The sixth step is to calculate the controller parameter Γ P，1 , Γ P，2 , Γ D，1 and Γ D，2 The value is

[0143] ...

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Abstract

The invention discloses a control method and system of high temperature gas cooled reactor power, relating to the technical field of nuclear energy science and engineering, wherein the method includes the steps as follows: S1, setting a nuclear power controller parameter and a reactor core outlet hot helium temperature controller parameter; S2, the reactor core outlet hot helium temperature controller calculating the deviation between the reactor core outlet hot helium temperature measuring value and the core outlet hot helium temperature reference value to obtain the modification of the relative nuclear power reference value; the nuclear power controller calculating the deviation between the reactor core relative neutron flux density measuring value and the relative neutron flux density reference value and obtaining a rod speed signal that drives the control rod to move. The invention real-time obtains and calculates the core outlet hot helium temperature measuring value and the reactor core relative neutron flux density measuring value of the high temperature gas cooled reactor, obtains the rod speed signal for driving the control rod and controls the high temperature gas cooled reactor power.

Description

technical field [0001] The invention relates to the field of nuclear energy science and engineering technology, in particular to a power control method and system for a high-temperature gas-cooled reactor. Background technique [0002] Due to its inherent safety and potential economic competitiveness, the high-temperature gas-cooled reactor has been recognized by the world nuclear energy community as one of the preferred reactor types with the characteristics of the fourth-generation nuclear energy system. The development of high-temperature gas-cooled reactor technology is of great significance to the sustainable development of my country . The high-temperature gas-cooled reactor uses ceramic-coated fuel elements, uses helium as the coolant, and graphite as the moderator and structural material. Its inherent safety is guaranteed by low power density, elongated core and strong temperature negative feedback effect . Safe, stable and efficient operation is the most critical p...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C7/36G21C17/00
CPCY02E30/33Y02E30/39Y02E30/30
Inventor 董哲黄晓津张作义吴宗鑫
Owner CHINERGY CO LTD
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