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An Improved Core Power Distribution Measurement Method Based on Instantaneous Gamma Response Correction

A technology of core power distribution and measurement method, which is applied in reactor, nuclear reactor monitoring, greenhouse gas reduction, etc., can solve the problem of large deviation between neutron detector predicted current and measured current, large deviation of core power distribution measurement, and disregard of instantaneous The influence of gamma effect and other issues

Active Publication Date: 2021-03-30
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The power distribution measurement method based on self-powered neutron detectors currently used in commercial PWRs does not consider the influence of instantaneous gamma effects
This simplified processing method makes the predicted current of some neutron detectors deviate greatly from the measured current in some cases, which in turn leads to a large deviation in the core power distribution measurement

Method used

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  • An Improved Core Power Distribution Measurement Method Based on Instantaneous Gamma Response Correction
  • An Improved Core Power Distribution Measurement Method Based on Instantaneous Gamma Response Correction
  • An Improved Core Power Distribution Measurement Method Based on Instantaneous Gamma Response Correction

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Embodiment 1

[0036] In order to understand the present invention more clearly, the core power distribution measuring device and operation method of a 1400MWe class nuclear power plant pressurized water reactor are taken as an example to illustrate.

[0037] Such as figure 1 As shown, the reactor core 1 is loaded with 193 boxes of fuel assemblies 8, and the arrangement of the fuel assemblies 8 in the core is as follows figure 2 shown. 89 bundles of control rods 2 are arranged in the reactor core 1, which are used for reactivity and power distribution control during the operation of the reactor, and to realize rapid shutdown. The arrangement of the control rods in the core is as follows: figure 2 shown. A total of 48 self-powered neutron detector assemblies are arranged in the core, and the layout of the self-powered neutron detector assemblies in the core is as follows: figure 2 shown. Each self-powered neutron detector assembly contains 7 detector elements, and the whole stack has a...

Embodiment 2

[0048] The method proposed by the present invention has been verified by using the data obtained from the operation of the pressurized water reactor unit A and unit B respectively. Firstly, the stable power operation state of the reactor is monitored by the response of the self-powered neutron detector in the reactor during the rapid drop of the control rods. Current, record the response current of all self-powered neutron detectors in the reactor as a function of time, and the recording time interval is 1s; then determine the instantaneous gamma of each self-powered neutron detector according to the detector response current recorded before and after the rapid shutdown Response share (γ=(I t -I n ) / I t ); and then use the determined instantaneous gamma response share to correct the measurement current of the self-powered neutron detector during the measurement process, and improve the measurement accuracy of the core power distribution.

[0049] Table 1 shows the measuremen...

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Abstract

A measurement method of improved core power distribution based on instantaneous Gamma response correction includes the following steps: monitoring the response signals of self-energetic neutron detectors in the reactor during the reactor shutdown process when the reactor is quickly inserted into the reactor core by the control rod from a stable power operation state, and recording the changes of the response signals of all self-energetic neutron detectors in the reactor core with time; according to the detector response current recorded before and after the rapid shutdown, determining the instantaneous gamma response share of the self-energetic detector; through the core on-line monitoring system, using the instantaneous gamma response share to correct the measurement current of the self-energetic neutron detector in the measurement process or the predicted current of the self-energetic neutron detector in the prediction process to reconstruct the core power distribution; effectively improving the measurement current-predicting current deviation of the self-energetic neutron detector in reactor, improving the measurement accuracy of core power distribution in the core on-line monitoring system, and improving the monitoring accuracy of safety parameters such as maximum linear power density, nuclear enthalpy rise heat pipe factor and minimum deviation bubble-nucleus boiling ratio.

Description

technical field [0001] The invention relates to a measurement method, in particular to a measurement method for improving core power distribution based on instantaneous gamma response correction. Background technique [0002] Core power distribution is an important parameter for core operation monitoring or supervision to ensure that parameters such as maximum linear power density, nuclear enthalpy rise heat pipe factor, and minimum deviation from nucleate boiling ratio meet safety limits and ensure the integrity of the fuel rod barrier. The core power distribution measurement is used to verify the rationality of the core design parameters, the conservatism of the accident analysis parameters, and the calibration of nuclear detectors outside the core during the core start-up phase, and to detect abnormal power distribution and monitor fuel burnup during the core operation phase Distribution, verification and calibration of extracore nuclear detectors. Commercial pressurized...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00G21C17/10
CPCG21C17/00G21C17/10Y02E30/30
Inventor 毕光文汤春桃杨波施建锋费敬然张宏博彭良辉杨伟焱秦玉龙杜炳
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD