Irradiation creep and IASCC prediction method of PWR's core internal: Verification of "Inspection and Evaluation Guideline for Reactor Internals of PWR(Baffle Former Bolt)"

PWR's core internals have aging due to IASCC (Irradiation Assisted Stress Corrosion Cracking). Although stress influences the occurrence of IASCC greatly, we have little data about PWR's irradiation creep which reduces stress. In this report, we assessed irradiation creep by using the remo...

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Veröffentlicht in:QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY 2005, Vol.23(1), pp.77-81
Hauptverfasser: KAMEYAMA, Masashi, CHIGUSA, Naoki, KUBO, Noboru, KATAYAMA, Masaaki
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container_title QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY
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creator KAMEYAMA, Masashi
CHIGUSA, Naoki
KUBO, Noboru
KATAYAMA, Masaaki
description PWR's core internals have aging due to IASCC (Irradiation Assisted Stress Corrosion Cracking). Although stress influences the occurrence of IASCC greatly, we have little data about PWR's irradiation creep which reduces stress. In this report, we assessed irradiation creep by using the removal torque of the baffle former bolts at the time of replacement. Then, we concluded that irradiation creep in PWR is approximately 50% of the irradiation creep in the fast breeder reactor. Moreover, we used this result to check the method for IASCC prediction method proposed in the last report which is applicable also to barrel former bolt and weld metal of barrel, and we confirmed the applicability of the IASCC prediction method for the actual plant.
doi_str_mv 10.2207/qjjws.23.77
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source J-STAGE (Japan Science & Technology Information Aggregator, Electronic) Freely Available Titles - Japanese; EZB-FREE-00999 freely available EZB journals
subjects Baffle former bolt
Barrel former bolt
Core internal
IASCC
Irradiation creep
Weld metal of barrel
title Irradiation creep and IASCC prediction method of PWR's core internal: Verification of "Inspection and Evaluation Guideline for Reactor Internals of PWR(Baffle Former Bolt)"
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