KR101250334B1 - Apparatus and method of vibration measurement for comprehensive vibration assessment of reactor vessel internals - Google Patents
Apparatus and method of vibration measurement for comprehensive vibration assessment of reactor vessel internals Download PDFInfo
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- KR101250334B1 KR101250334B1 KR1020120005691A KR20120005691A KR101250334B1 KR 101250334 B1 KR101250334 B1 KR 101250334B1 KR 1020120005691 A KR1020120005691 A KR 1020120005691A KR 20120005691 A KR20120005691 A KR 20120005691A KR 101250334 B1 KR101250334 B1 KR 101250334B1
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- G01H9/00—Measuring mechanical vibrations or ultrasonic, sonic or infrasonic waves by using radiation-sensitive means, e.g. optical means
- G01H9/008—Measuring mechanical vibrations or ultrasonic, sonic or infrasonic waves by using radiation-sensitive means, e.g. optical means by using ultrasonic waves
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Abstract
Description
본 발명은 원자로 내부구조물의 종합진동평가를 위한 진동 측정장치 및 측정방법에 관한 것으로서, 더욱 상세하게는 노심지지배럴(core support barrel; CSB), 상부안내구조물(upper guide structure; UGS) 그리고 하부지지구조물(lower support structure; LSS)의 진동을 측정하되, 원자로 내부구조물의 설계 변경 및 측정용 구조물의 설치와 제거 없이 진동을 측정할 수 있도록 하는 원자로 내부구조물 종합진동평가를 위한 진동 측정장치 및 진동 측정방법에 관한 것이다.
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a vibration measuring apparatus and a measuring method for comprehensive vibration evaluation of a reactor internal structure, and more particularly, a core support barrel (CSB), an upper guide structure (UGS) and a lower support. Vibration measuring device and vibration measurement for measuring the vibration of the lower support structure (LSS), but for measuring vibration without changing the design of the reactor internal structure and installing and removing the measurement structure. It is about a method.
원자로 내부구조물(reactor vessel internals : RVI)은 원자로(reactor vessel)의 정상(steady) 및 과도(transient) 운전 조건하에서 원자로 냉각재 유동에 의해 진동을 겪게 되므로 원자력 발전소의 전 수명기간 동안 그 건전성이 유지되고, 안전 여유도가 확보되고 있음을 실제 원자로를 대상으로 입증해야 한다. 이를 위해서 원자로 내부구조물에 대한 종합진동평가(Comprehensive vibration assessment program; CVAP)가 수행된다.Reactor vessel internals (RVI) are subjected to vibrations from the reactor coolant flow under steady and transient operating conditions in the reactor vessel, thus maintaining their integrity throughout the life of the nuclear power plant. In other words, it should be demonstrated in actual reactors that safety margins are secured. To this end, a Comprehensive Vibration Assessment Program (CVAP) is carried out on the reactor internals.
원자로 내부구조물 종합진동평가는 해석(analysis), 측정(measurement) 그리고 검사(inspection)로 구성되는데, 측정은 시운전 시험 중에 핵연료가 장전되기 전(pre-core)의 원자로에 대해 원자로 고온기능시험(hot functional test; HFT)시 수행되며, 해석으로부터 산출된 원자로의 정상운전 및 과도운전 상태에서의 진동 예측값을 확인하고, 60년의 전 수명기간 동안의 운전에 대한 안전 여유도를 결정하기 위한 것이다.Comprehensive vibration assessment of the reactor internal structure consists of analysis, measurement, and inspection, which are carried out on a reactor hot function test for the reactor pre-core during the commissioning test. It is performed during the functional test (HFT), to check the vibration prediction values in the normal operation and the transient operation state of the reactor calculated from the analysis, and to determine the safety margin for operation for the entire life of 60 years.
원자로 내부구조물 종합진동평가를 위한 진동 측정장치 및 측정용 구조물의 설계와 제작을 위해서는 측정위치와 측정항목을 사전에 신중하게 선정해야 한다. 원자로 내부구조물 종합진동평가는 진동 해석결과와 측정결과를 비교, 평가해야 하므로 해석결과에 근거하여 측정위치와 측정항목을 선정하여야 한다.In order to design and manufacture the vibration measuring device and the measurement structure for the comprehensive vibration evaluation of the reactor internal structure, the measurement position and the measurement items should be carefully selected in advance. The comprehensive vibration evaluation of the reactor internal structure must compare and evaluate the vibration analysis result and the measurement result. Therefore, the measurement position and the measurement item should be selected based on the analysis result.
기존에는 원자로 내부구조물 종합진동평가를 위해서 진동 측정센서를 원자로 내부구조물에 부착하고, 원자로 상부 헤드에 위치한 압력경계관통부에서 데이터취득시스템까지 측정케이블로 연결되었다.In the past, a vibration measuring sensor was attached to the reactor internal structure for comprehensive vibration evaluation of the reactor internal structure, and it was connected to the data acquisition system from the pressure boundary through-hole located at the upper head of the reactor.
그런데, 원자로 내부의 구조가 복잡하여, 진동 측정센서를 설치하고 측정 케이블을 연결하기 위해서는 원자로 내부구조물의 구조를 변경해야 하고, 이를 원자로 내부구조물에 설치하기 위한 측정용 구조물을 추가적으로 설계, 제작 및 설치해야 하며, 측정 후에는 이를 제거해야 하는 등 많은 문제점이 있었다.
However, since the structure inside the reactor is complicated, in order to install the vibration measuring sensor and connect the measurement cable, the structure of the reactor internal structure must be changed, and the measurement structure for installing it on the reactor internal structure is additionally designed, manufactured and installed. There are many problems, such as the need to remove it after measurement.
본 발명은 원자로 내부구조물에서 노심지지배럴(core support barrel ; CSB), 상부안내구조물(upper guide structure; UGS) 그리고 하부지지구조물(lower support structure; LSS)의 진동을 측정할 수 있는 진동 측정장치와 진동 측정방법을 제공하기 위한 것이다.The present invention provides a vibration measuring device capable of measuring vibrations of a core support barrel (CSB), an upper guide structure (UGS) and a lower support structure (LSS) in a reactor internal structure. It is to provide a vibration measuring method.
또한 본 발명은 원자로 내부구조물의 설계 변경 및 측정용 구조물의 설치와 제거 없이 진동을 측정할 수 있는 진동 측정장치 및 진동 측정방법을 제공하기 위한 것이다.
In another aspect, the present invention is to provide a vibration measuring device and a vibration measuring method that can measure the vibration without changing the design of the reactor internal structure and the installation and removal of the measurement structure.
본 발명은 원자로 내부구조물의 진동측정 방법으로서, 원자로 상부 헤드면과, 원주면과, 하부 헤드면에 각각 진동측정센서를 설치하고 외부에 데이터 취득시스템윽 구비하여 원자로 외부에 진동 측정장치를 설치하여 원자로 내부구조물의 노심지지배럴, 상부안내구조물 그리고 하부지지구조물의 진동을 측정하여 분석 평가하는 것을 특징으로 한다.The present invention is a vibration measuring method of the internal structure of the reactor, the vibration measuring sensor is installed on the upper head surface, the circumferential surface, and the lower head surface of the reactor, and the data acquisition system is provided outside to install the vibration measuring device outside the reactor. It is characterized by measuring and analyzing the vibration of the core support barrel, the upper guide structure and the lower support structure of the reactor internal structure.
본 발명은, 원자로 내부구조물의 노심지지배럴, 상부안내구조물 그리고 하부지지구조물의 진동을 측정하기 위한 진동 측정장치로서, 노심지지배럴, 상부안내구조물 및 하부지지구조물의 진동을 측정하기 위한 데이터 취득시스템을 원자로 외부에 설치하고, 상기 데이터 취득시스템으로 원자로의 진동을 측정하여 전송하기 위하여 원자로 상부 헤드면의 측정부와; 원자로 원주면의 측정부와; 원자로 하부 헤드면 측정부를 구비하고, 상기 진동 측정장치의 상부 헤드면 측정부, 원주면 측정부 및 하부 헤드면 측정부는 다수의 초음파 센서로 구성된다.The present invention is a vibration measuring device for measuring the vibration of the core support barrel, the upper guide structure and the lower support structure of the reactor internal structure, the data acquisition system for measuring the vibration of the core support barrel, the upper guide structure and the lower support structure A measurement unit on the upper head of the reactor for installing the outside of the reactor and measuring and transmitting vibration of the reactor to the data acquisition system; A measuring unit on the reactor circumferential surface; A nuclear reactor lower head surface measuring unit is provided, and the upper head surface measuring unit, the circumferential surface measuring unit, and the lower head surface measuring unit of the vibration measuring device include a plurality of ultrasonic sensors.
진동 측정장치는 원자로 외부 원주면에 구비된 진동 측정센서를 사용하여 노심지지배럴의 진동을 측정하고, 그리고 진동 측정장치는 상부 헤드면에 구비된 진동 측정센서를 이용하여 상부안내구조물의 진동을 측정할 수 있다. 또한 진동 측정장치는 원자로의 하부 헤드면에 구비된 진동 측정센서를 이용하여 하부지지구조물의 진동을 측정할 수 있다.The vibration measuring device measures the vibration of the core support barrel using the vibration measuring sensor provided on the outer circumferential surface of the reactor, and the vibration measuring device measures the vibration of the upper guide structure using the vibration measuring sensor provided on the upper head surface. can do. In addition, the vibration measuring apparatus may measure the vibration of the lower support structure by using the vibration measuring sensor provided on the lower head surface of the reactor.
이와 같이 측정된 값을 원자로에 구비된 데이터 취득시스템에 저장 및 분석하여 노심지지배럴, 상부안내구조물 그리고 하부지지구조물dp 발생되는 유동유발진동(flow-induced vibration ; FIV)에 따른 원자로 내부구조물의 구조적 건전성과 안전여유도 확보 여부를 평가할 수 있다.
The measured values are stored and analyzed in the data acquisition system provided in the reactor, and the structural structure of the reactor internal structure according to the flow-induced vibration (FIV) generated by the core support barrel, the upper guide structure and the lower support structure dp is generated. Health and safety margins can be assessed.
이와 같이 본 발명은 원자로의 상부 헤드면 측정부와, 원주면 측정부와, 하부 헤드면 측정부를 구비하고 초음파센서를 이용하여 원자로 외부에서 노심지지배럴, 상부안내구조물 그리고 하부지지구조물의 유동유발진동을 측정하여 데이터 취득 시스템에서 저장 및 분석 처리하도록 구성함으로써, 진동 측정을 위한 진동 측정용 계측기나 측정케이블 등을 원자로 내부에 설치하기 위해서 원자로 내부구조물의 설계변경, 설계변경에 따른 구조물 응력해석 및 그에 따른 제작, 설치 공정의 추가 등이 불필요하여 진동측정 및 설비와 진동평가 비용을 대폭 절감할 수 있다.As described above, the present invention includes an upper head plane measuring unit, a circumferential plane measuring unit, and a lower head plane measuring unit of a nuclear reactor, and uses the ultrasonic sensor to induce flow vibration of the core support barrel, the upper guide structure and the lower support structure outside the reactor. The system is configured to measure and store the data in the data acquisition system, and to store and analyze the data.In order to install a vibration measuring instrument or measuring cable inside the reactor for vibration measurement, the structural stress analysis according to the design change and the design change of the reactor internal structure This eliminates the need for additional manufacturing and installation processes, which can significantly reduce the cost of vibration measurement and equipment and vibration evaluation.
또한 원자로를 제작하고 설치한 후 시운전 준비기간 동안 진동 측정센서를 설치하여 원자로 내부구조물의 진동 측정을 수행할 수 있으므로 원전 건설 주공정에 미치는 영향을 최소화 할 수 있다는 효과가 있다.
In addition, since the vibration measurement of the internal structure of the reactor can be performed by installing the vibration measuring sensor during the preparation period for commissioning after the reactor is manufactured and installed, the effect on the main process of nuclear power plant construction can be minimized.
도 1은 본 발명에 의한 원자로 내부구조물 종합진동평가를 위한 진동 측정장치의 구성도.1 is a block diagram of a vibration measuring apparatus for the overall vibration evaluation of the reactor internal structure according to the present invention.
이하, 본 발명의 실시 예를 첨부된 도면을 참조해서 상세히 설명하면 다음과 같다.Hereinafter, embodiments of the present invention will be described in detail with reference to the accompanying drawings.
도 1은 본 발명에 의한 원자로 내부구조물 종합진동평가를 위한 진동 측정장치의 구성도이다.1 is a block diagram of a vibration measuring apparatus for the overall vibration evaluation of the reactor internal structure according to the present invention.
원자로 내부구조물의 노심지지배럴(11), 상부안내구조물(12) 및 하부지지구조물(13)의 진동을 측정하여 분석 평가하는 데이터 취득시스템(20)을 원자로(10)의 외부에 설치하고, 원자로(10)의 진동을 측정하여 상기 데이터 취득시스템(20)으로 전송하도록 측정 케이블(25)로 연결되고, 원자로(10) 상부 헤드면에 진동측정 센서(24)들을 설치한 상부 헤드면 측정부(21)와; 원자로(10) 원주면에 진동측정 센서(24)들을 설치한 원주면 측정부(22)와; 원자로(10) 하부 헤드면에 진동측정 센서(24)들을 설치한 하부 헤드면 측정부(23)를 구비하고, 상기 상부 헤드면 측정부(21), 원주면 측정부(22) 및 하부 헤드면 측정부(23)는 진동측정 센서(24)들로 초음파 센서를 설치하여 구성된다.A
이와 같이 본 발명은, 원자로(10)의 외측면에 진동측정 센서(24)로서 초음파 센서를 설치하되, 원자로(10)의 원주면에 다수의 진동측정센서(24)를 설치하여 노심지지배럴의 진동을 측정한다.As described above, the present invention provides an ultrasonic sensor as the
그리고, 원자로(10) 상부 헤드면에 다수의 진동측정센서(24)를 설치하여 상부안내구조물의 진동을 측정한다.Then, a plurality of
또한, 원자로(10) 하부 헤드면에 다수의 진동측정센서(24)를 설치하여 하부지지구조물(13)의 진동을 측정할 수 있다. 여기서, 각 측정부들의 진동측정센서(24)들은 각각의 위치에 따라 일정한 간격으로 분산 설치되고, 측정된 센서값들은 데이터 취득시스템(20)으로 측정 케이블(25)을 통해 전송한다.In addition, by installing a plurality of
따라서, 상기 진동측정센서(24)들이 원자로(10)의 외측면에 설치되어 있으므로, 내부구조물의 영향 없이 외부에서 측정 케이블(25)을 연결하여 데이터 취득시스템(20)에 연결할 수 있다.Therefore, since the
그러므로, 외부에 설치되는 진동측정센서(24), 측정케이블(25) 및 데이터 취득시스템(20)을 이용하여 원자로(20) 내부구조물의 진동을 측정하므로, 측정을 위한 진동측정센서(24)나, 측정케이블(25) 등을 원자로 내부에 설치하기 위해서 원자로 내부구조물의 설계 변경, 설계 변경에 따른 구조물의 응력해석 및 그에 따른 제작과 설치 공정의 추가 등이 불필요하게 된다.Therefore, since the vibration of the internal structure of the
또한, 원자로(10)를 제작하고 설치한 후 시운전 준비기간 동안 진동 측정장치를 설치하여 원자로 내부구조물의 진동측정을 수행할 수 있으므로, 원전 건설 주공정에 미치는 영향을 최소화 할 수 있다.
In addition, after the production and installation of the
10 : 원자로 11 : 노심지지배럴
12 : 상부안내구조물 13 : 하부안내구조물
20 : 데이터취득시스템 21 : 상부 헤드면 측정부
22 : 원주면 측정부 23 : 하부 헤드면 측정부
24 : 진동측정센서 25 : 측정케이블10: reactor 11: core support barrel
12: upper guide structure 13: lower guide structure
20: data acquisition system 21: upper head surface measuring unit
22: circumferential surface measuring unit 23: lower head surface measuring unit
24: vibration measuring sensor 25: measuring cable
Claims (4)
원자로 외부에 데이터 취득 시스템을 구비하고, 원자로의 상부 헤드면과, 원자로의 몸체 원주면과, 원자로의 하부 헤드면의 외측면에 각각 복수의 진동측정센서를 설치하여 원자로 외부에 설치된 데이터 취득시스템에 진동 측정케이블로 연결하고, 상기 데이터 취득 시스템에서 진동측정센서들의 데이터를 입력받아 원자로 내부구조물의 상부안내구조물, 노심지지배럴, 하부지지구조물의 진동을 측정하여 분석 및 평가하는 것을 특징으로 하는 원자로 내부구조물의 종합진동평가를 위한 진동 측정방법.
In the vibration measuring method for the comprehensive vibration evaluation of the reactor internal structure,
A data acquisition system is provided outside the reactor, and a plurality of vibration measuring sensors are provided on the upper head face of the reactor, the circumferential face of the reactor body, and the outer face of the lower head face of the reactor, respectively. Reactor internal vibration, characterized in that for measuring the vibration of the upper guide structure, the core support barrel, the lower support structure of the reactor internal structure by receiving the vibration measurement cable, the data obtained from the vibration measurement sensors from the data acquisition system Vibration measurement method for comprehensive vibration evaluation of structures.
초음파 센서를 이용하는 것을 특징으로 하는 원자로 내부구조물의 종합진동평가를 위한 진동 측정방법.
According to claim 1, wherein the vibration measuring sensor,
Vibration measurement method for the comprehensive vibration evaluation of the internal structure of the reactor, characterized by using an ultrasonic sensor.
원자로(10) 상부 헤드면에 진동측정 센서(24)들을 설치한 상부 헤드면 측정부(21)와;
원자로(10) 원주면에 진동측정 센서(24)들을 설치한 원주면 측정부(22)와;
원자로(10) 하부 헤드면에 진동측정 센서(24)들을 설치한 하부 헤드면 측정부(23)와;
상기 상부 헤드면 측정부(21)의 진동측정 데이터에 의거하여 상부안내구조물(12)의 진동을 측정 분석 평가하고, 상기 원주면 측정부(22)의 진동측정 데이터에 의거하여 노심지지배럴의 진동을 측정 분석 평가하며, 상기 하부 헤드면 측정부(23)의 진동측정 데이터에 의거하여 하부지지구조물(13)의 진동을 측정 분석 평가하도록 원자로 외부에 설치되는 데이터 취득시스템(20)과;
상기 상부 헤드면 측정부(21)와, 상기 원주면 측정부(22)와, 상기 하부 헤드면 측정부(23)에 각각 설치된 복수의 진동측정센서들의 측정데이터를 상기 데이터 취득시스템(20)으로 전송하도록 연결 및 설치되는 진동 측정케이블(25)을 포함하여 구성된 것을 특징으로 하는 원자로 내부구조물의 종합진동평가를 위한 진동 측정장치.
In the vibration measuring device for the comprehensive vibration evaluation of the reactor internal structure,
An upper head surface measuring unit 21 having vibration measuring sensors 24 installed on the upper head surface of the reactor 10;
A circumferential surface measuring unit 22 having vibration measuring sensors 24 installed on a circumferential surface of the reactor 10;
A lower head surface measuring unit 23 having vibration measuring sensors 24 installed on the lower head surface of the reactor 10;
Measuring and evaluating the vibration of the upper guide structure 12 based on the vibration measurement data of the upper head surface measuring unit 21, and the vibration of the core support barrel based on the vibration measuring data of the circumferential surface measuring unit 22. A data acquisition system 20 installed outside the reactor to measure, analyze, evaluate, and evaluate and analyze the vibration of the lower support structure 13 based on the vibration measurement data of the lower head surface measuring unit 23;
Measurement data of a plurality of vibration measuring sensors respectively installed in the upper head surface measuring unit 21, the circumferential surface measuring unit 22, and the lower head surface measuring unit 23 is transferred to the data acquisition system 20. Vibration measuring device for the comprehensive vibration evaluation of the reactor internal structure, characterized in that it comprises a vibration measuring cable 25 is connected and installed to transmit.
초음파 센서를 이용하는 것을 특징으로 하는 원자로 내부구조물의 종합진동평가를 위한 진동 측정장치.
The vibration measuring sensor 24 of claim 3,
Vibration measuring device for the comprehensive vibration evaluation of the internal structure of the reactor, characterized by using an ultrasonic sensor.
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Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH11125688A (en) | 1997-10-23 | 1999-05-11 | Tokyo Electric Power Co Inc:The | Reactor vibration monitor |
JP2011053092A (en) | 2009-09-02 | 2011-03-17 | Toshiba Corp | Nuclear instrumentation system |
JP2011133241A (en) | 2009-12-22 | 2011-07-07 | Toshiba Corp | System and method for monitoring vibration of nuclear reactor |
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Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH11125688A (en) | 1997-10-23 | 1999-05-11 | Tokyo Electric Power Co Inc:The | Reactor vibration monitor |
JP2011053092A (en) | 2009-09-02 | 2011-03-17 | Toshiba Corp | Nuclear instrumentation system |
JP2011133241A (en) | 2009-12-22 | 2011-07-07 | Toshiba Corp | System and method for monitoring vibration of nuclear reactor |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111024347A (en) * | 2019-12-26 | 2020-04-17 | 华中科技大学 | Reactor health state assessment method |
CN111024347B (en) * | 2019-12-26 | 2021-11-02 | 华中科技大学 | Reactor health state assessment method |
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