• Title/Summary/Keyword: Top-Mounted In-Core Instrumentation

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TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES

  • KIM, SUNG JUN;KANG, TAE KYO;CHO, YEON HO;CHANG, SANG GYOON;LEE, DAE HEE;MAENG, CHEOL SOO
    • Journal of Energy Engineering
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    • v.24 no.2
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    • pp.154-166
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    • 2015
  • The in-core instrumentation measures core power distribution and coolant temperature in local regions of the core in pressurized water reactors. The installation types are distinguished by the designs of routing paths that exit either through reactor bottom mounted instrument nozzles or through reactor top mounted instrument nozzles. Although each type has unique advantages, it is generally known that top mounted design is more competitive with respect to emphasizing nuclear safety issues and ability to cope with severe accidents. The international nuclear vendors have provided various types of reactors with top mounted design. Nuclear power reactors in Korea, however, only have been designed to be applicable to the use of bottom mounted design, and it has been pointed out that the capabilities of Korean reactors against severe accidents should be further enhanced. The paper deals with technical issues on reactor internal and external design, in-core instrumentation, support assembly, sealing mechanism with nozzles, handling, and analytical issues in order to establish the ways of development.

Environmental Fatigue Evaluation of Top-Mounted In-Core Instrumentation Nozzle (상부 탑재형 노내계측기 노즐의 환경피로평가)

  • Yoon, Hyo-Sub;Kim, Jong-Min;Maeng, Cheol-Soo;Kim, Gee-Seok;Kim, Hyun-Min
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.29 no.3
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    • pp.245-252
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    • 2016
  • The development of Top-Mounted In-Core Instrumentation(TM-ICI) is an ongoing project to reduce the risk due to severe accidents by inserting the instrumentation into a reactor closure head instead of a reactor bottom head. As part of this project, environmental fatigue analyses for TM-ICI nozzle have been performed using two methods of NUREG/CR-6909 and Code Case N-761. TM-ICI nozzle is subjected to transient loads for level A, level B and test conditions that should be evaluated for a fatigue analysis. It is found that a cumulative usage factor considering reactor coolant environment for TM-ICI nozzle is evaluated as less than 1, which is ASME Code allowable criteria of a fatigue analysis.