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Method for measuring reactivity value of control rod of high-temperature gas cooled reactor

A high-temperature gas-cooled reactor and reactivity technology, applied in the direction of reactors, greenhouse gas reduction, climate sustainability, etc., can solve the problem that the reactivity instrument cannot apply the reactivity value of high-temperature gas-cooled reactor control rods, etc. Achieve the effects of reducing R&D and equipment procurement costs, good operability, and reducing engineering investment

Pending Publication Date: 2022-07-12
HUANENG SHANDONG SHIDAOBAY NUCLEAR POWER CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] Due to the different characteristics of high-temperature gas-cooled reactors and pressurized water reactors, the current reactivity instrument cannot be applied to high-temperature gas-cooled reactors to measure the reactivity value of high-temperature gas-cooled reactor control rods

Method used

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  • Method for measuring reactivity value of control rod of high-temperature gas cooled reactor

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Embodiment Construction

[0029] Various exemplary embodiments of the present application will now be described in detail with reference to the accompanying drawings. It should be noted that the relative arrangement of the components and steps, the numerical expressions and numerical values ​​set forth in these embodiments do not limit the scope of the present application unless specifically stated otherwise.

[0030] The following will describe in detail the embodiments of the present application, examples of which are illustrated in the accompanying drawings, wherein the same or similar reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain the present application, but should not be construed as a limitation on the present application. Based on the embodiments in this application, all other embodiments obtained by those o...

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Abstract

The invention provides a method for measuring the reactivity value of a control rod of a high-temperature gas cooled reactor, and the method comprises the following steps: S1, enabling a rod to be measured to be located at a first preset position, and enabling a reactivity compensation rod to be located at a second preset position; the power compensation rod is located at a preset high position; s2, starting the reactor, and measuring the first multiplication period; s3, adjusting the position of the rod to be measured and lifting the power compensation rod; measuring the second multiplication period; s4, the position of the reactive compensation rod is adjusted, the power compensation rod is lifted, and the third multiplication period is measured; and S5, repeating the steps S3 to S4, and calculating the reactivity value of the measured rod according to each progressive period of the reactor. One technical effect of the embodiment of the invention is that the design is reasonable, the reactivity value of the control rod can be accurately measured, and the operability is relatively good.

Description

technical field [0001] The invention belongs to the technical field of high-temperature gas-cooled reactor debugging and operation, and particularly relates to a method for measuring the reactivity value of a control rod of a high-temperature gas-cooled reactor. Background technique [0002] For the pebble bed type high temperature gas-cooled reactor, two sets of reactivity control systems are designed on the graphite side reflector, one is the control rod system, and the other is the absorption ball shutdown system with different working principles and independent. Among them, the control rod system is the main reactive control method, which realizes the following functions: 1) reactive control of operating conditions such as reactor startup, lifting power, and normal power operation adjustment; 2) emergency shutdown; 3) only using control rods A system that enables the reactor to reach and maintain a normal shutdown state. [0003] In practical applications, the PWR nucle...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/104G21C17/06
CPCG21C17/104G21C17/06Y02E30/30
Inventor 贺启超李志容罗勇李海穹刘福成王栋栋丰星韩芳刘峰峰孙福瑞
Owner HUANENG SHANDONG SHIDAOBAY NUCLEAR POWER CO LTD
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