Abstract This paper discusses the possibility of in-situ evaluation of crack propagation using Eddy Current Monitoring (ECM) system in a Boiling Water Reactor (BWR) environment. For the purpose, an ECM experiment was conducted at the System Safety Benchma rk Facility (SSBF). The target for the monitoring was a large-scale pipe specimen made of austenitic stainless steels 304L, 316L, and carbon steel STS410, connected by weld joints of nickel based alloy 182. Slits were prepared at the Heat Affected Zones (...
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In-situ Crack Evaluation using Eddy Current Monitoring in a Boiling Water Reactor Environment

A Proactive Materials Degradation Management (PMDM) project has been carried out at the Frontier Research Initiative (FRI), New Industry Creation Hatchery Center, Tohoku University for 5 years, as a part of a Nuclear Industries Safety Agency (NISA, now the Secretariat of the Nuclear Regulation Authority) project that was originally formed in 2007 to define an Aging Management Program that addresses unexpected structural material failures in Light Water Reactors (LWRs). Such a program required, therefor...
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Proactive Evaluation of Potential and Latent Materials Degradation Phenomena by PIRT

This study proposes an innovative technique for repairing of cracked or damaged parts of structures, such as nuclear or thermal power plants, by means of cold gas dynamic spray (CS) technique. In the case of generation of cracks etc, in the structure, the cracks can be repaired by welding. However, the welding spends considerable time on repair, and also needs special skills. The CS techni que is known as a new technique not only for coatings but also for thick depositions. It has many advantages, i.e. ...
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Fundamental Study on Repairing Technique for Cracked or Damaged Parts of Structuresby Cold Gas Dynamic Spray Technique

A Proactive Materials Degradation Management (PMDM) project has been carried out at the Fronti er Research Initiative (FRI), New Industry Creation Hatchery Center, Tohoku University for 5 ye ars, as a part of a Nuclear Industries Safety Agency (NISA) project that was originally formed in 2007 to define an Aging Management Program that addresses unexpected structural material fa ilures in Light Water Reactors (LWRs). Such a program required, therefore, the development of a life prediction capability for sp...
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Proactive Evaluation of Potential/Latent Degradation Phenomena for Light Water Reactor Structural Materials and System Safety

An inside cladding of RPV in Hamaoka-5 caused pitting damage by sea water intrusion in 2011. For a restart of Hamaoka-5, we need a conservative evaluation such that SCC propagates instead of pitting. Two years ago, we reported metallurgical observation results in advance of SCC tests at AESJ conference. This is the progress report describing SCC test results obtained after the AESJ conference....
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A study on corrosion immunity of RPV inside cladding (2) Stress corrosion cracking test

The predictive and preventive maintenance technologies are of increasingly importance for the long term operation (LTO) of Light Water Reactor (LWR) plants. In order f or the realization of LTO, it is essential to prevent the degradation phenomena from emergence using proper maintenance programs on foreseeing the phenomena and evalua ting their rates of development. In this paper, the proactive activities and the aging degradation phenomenon which were discussed in the Proactive Aging Management Gro up Mee...
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Proactive Materials Degradation Management and Development ofCondition Monitoring Technology

Characterization of oxide film on the SCC fracture surface was examined by using TEM and Micro Raman Spectrosc opy. The SCC sample cut from cracked component of the Onagawa Nuclear Power Plant was compared to CT-type labo ratory samples. The a-Fe2O3 distribution in the outer layer of the oxide film was the most characteristic of c rack growth rate. The enrichment of Cr was observed at crack tip and inner layer of all SCC samples with TEM....
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Evaluation of Oxide Film on the Surface of SCC at Onagawa Nuclear Power Plant

A Proactive Materials Degradation Management (PMDM) project has been carried out at the Frontier Research Initiative (FRI), New Industry Creation Hatchery Center, Tohoku University for 5 yea rs, as a part of a Nuclear Industries Safety Agency (NISA, now the Secretariat of the Nuclear Regulation Authority) project that was originally formed in 2007 to define an Aging Management P rogram that addresses unexpected structural material failures in Light Water Reactors (LWRs). Such a program required, therefore,...
英字タイトル:
Proactive Evaluation of Potential and Latent Materials Degradation Phenomena

This paper discusses the possibility of in-situ quantitative evaluation of crack propagation using Eddy Current Monitoring (ECM) system in a Boiling Water Reactor (BWR) environment. For the purpose, ECM experiment was conducted at a System Safety Benchmark Facility (SSBF). The target for the monitoring was a large-scale pipe specimen made of austenitic stainless steels 304L, 316L, and carbon steel STS410, connected by weld joints of nickel based alloy 182 within the SSBF. Slits were prepared at the H...
英字タイトル:
Quantitative Monitoring of Crack Propagation in High Temperature Environment Using Eddy Current Testing

A 3D-FEM simulation code based on the deformation/oxidation model for the evaluation of SCC in comp act tension specimens was extended to evaluate the axial SCC behavior of mock-up specimens of botto m mount instrumentation tube of pressurized water reactor, and its applicability was investigated by comparing the cracking behavior calculated by the simulation with that obtained by the experiment....
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Stress Corrosion Cracking Test Methodology for inner axial cracks and its cracking behavior