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A Review of Measuring Sensors for Reactor Vessel Internals Comprehensive Vibration Assessment Program in Advanced Power Reactor 1400

APR1400 원자로 내부구조물 종합진동평가프로그램용 측정센서 검토

  • 고도영 (한국수력원자력(주) 원자력발전기술원) ;
  • 이재곤 (한국수력원자력(주) 원자력발전기술원)
  • Received : 2010.11.09
  • Accepted : 2010.12.08
  • Published : 2011.01.20

Abstract

Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. nuclear regulatory commission regulatory guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors because the measurement is conducted during the critical path of the construction period of nuclear power plants. Therefore, we analyzed RVI thermal-hydraulic and structure design data of Palo Verde nuclear power plant(U.S.), Yonggwang nuclear power plant(Korea) and APR1400 and researched measuring sensors used in them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected suitable measuring sensors for RVI CVAP in advanced power reactor 1400(APR1400).

Keywords

References

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