E-Journal of Advanced Maintenance (EJAM)


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Measures for Tsunami Striking Nuclear Power Station in Japan Special Article: The Great Tohoku Earthquake (1)
The Tragedy of “To Be” Principle in the Japanese Nuclear Industry
	Planning and Consideration on SFR R&D Activities in China
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	A New Mechanical Condition-based Maintenance Technology Using Instrumented Indentation Technique
	Survey robots for Fukushima Daiichi Nuclear Power Plant

Vol.17 No.2 (August, 2025)
Academic Articles
AA184	Regular Paper pp.15-24
	Method for Creating Large Datasets for Deep Learning to Improve Image Depth Accuracy	Masahiro MURAYAMA

Vol.17 No.1 (May, 2025)
Academic Articles
AA183	Regular Paper pp.1-14
	Development of performance loss function for the importance analysis of inspection in terms of risk of safety performance of a piping system	Akihiro MANO

Vol.16 No.2 (February, 2025)
Academic Articles
AA182	Regular Paper pp.12-20
	Performance Evaluation of Multivariate Time Series Anomaly Detection by Two-Stage Autoencoder using Power Plant Data	Yasunori TAGUCHI

Vol.16 No.1 (November, 2024)
Academic Articles
AA181	Regular Paper pp.1-11
	Improvement of Corrective Action Program (CAP) in Decommissioning Plant	Masao UESAKA

Vol.15 No.1 (February, 2024)
Academic Articles
AA180	Regular Paper pp.1-18
	Study of the Fundamental Concepts for Improving the Safety of Nuclear Power Plants	Takayuki AOKI

Vol.14 No.1 (August, 2022)
Academic Articles
AA179	Regular Paper pp.1-13
	Improved three-dimensional atom probe tomography procedures for analyzing irradiation-induced microstructures	Ba Vu Chinh NGUYEN et al.

Vol.13 No.2 (February, 2022)
Academic Articles
AA177	Regular Paper pp.1-13
	Long-term stability mechanism for the effect with WJP and buffing residual stress improving treatments	Lina YU et al.
AA178	Regular Paper pp.14-25
	Evaluation of the Capability to Estimate a Crack Profile by 3D SAFT-UT	Yoshinori KAMIYAMA et al.

Vol.13 No.1 (July, 2021)
Academic Articles
AA175	Regular Paper pp.1-11
	Tempering Effect Prediction of Temper Bead Repair Technology for BMI Penetration Nozzles	Lina YU et al.
AA176	Regular Paper pp.12-20
	A Novel Simulation Method of Thermal Cycle in Multi-pass Welding Process by Temper Bead Technique	Lina YU et al.


Vol.12 No.1 (May, 2020)
Academic Articles
Special Issue 23 (Guest editor: K . Suzuki ) "The 4th International Conference on Maintenance Science and Technology (ICMST-Tohoku 2018)"
AA172	Regular Paper pp.1-6
	Development of a Pipe-Wall Thinning Inspection Method Based on a Wireless UT Sensor	Akinori TAMURA et al.
AA173	Regular Paper pp.7-13
	Application of Charpy Specimens Reconstituted by Electron Beam Welding for the Evaluation of Irradiation Embrittlement of Reactor Pressure Vessels	Seiji SAKURAYA et al.

AA174	Regular Paper pp.14-25
	The effect of Dissolved Hydrogen for PWSCC Initiation test by Reverse U-Bend specimen of Alloy 600	Takaaki Kobayashi et al.
New Technology
NT97	Classification :7 - C	Dev. Level: Phase 1
	Ultrasonic Underwater Imaging Techniques for Visualizing Environments and Supporting Remote Operation	Hitachi-GE Nuclear Energy, Ltd. Hitachi, Ltd.


Vol.11 No.4 (February, 2020)
Academic Articles
Special Issue 22 (Guest editor: K. Suzuki ) "The 4th International Conference on Maintenance Science and Technology (ICMST-Tohoku 2018)"
AA165	Regular Paper pp.124-131
	Verification Benchmark Analysis of Structural Reliability Evaluation Codes for Fast Reactor Components	Shigeru TAKAYA et al.
AA166	Regular Paper pp.132-138
	Effective Utilization of Radiation Resistant RF Tag in the Decommissioning Work Management	Kunio ITO et al.
AA167	Regular Paper pp.139-146
	Corrosion Induced Roughness Characterization by Ultrasonic Attenuation Measurement	Hiroyuki NAKAMOTO et al.
AA168	Regular Paper pp.147-152
	Bayesian Evaluation of Damage Risk from Monitoring Data	Atsushi Iwasaki
AA169	Regular Paper pp.153-162
	Optimal Maintenance Scheduling in Nuclear Power Plants via Linear Programming Considering the Relationship between the Failure Cause and Maintenance Type	Masaaki SUZUKI et al.
AA170	Regular Paper pp.163-171
	Applicability of ultrasonic-wave based method for integrity assessment of concrete severely damaged by heat	Vu Nhut LUU et al.
AA171	Regular Paper pp.172-178
	Verification of Safety Margin of Reactor Pressure Vessel Exposed to Various Thermal Transients Based on Probabilistic Approach	Masahide SUZUKI et al.
New Technology
NT96	Classification :7 - A	Dev. Level: Phase 3
	The Development of Sampling Technology inside Reactor Vessel and Core Internal during PWR Decommissioning of Japan	Mitsubishi Heavy Industries, Ltd.


Vol.11 No.3 (November, 2019)
Academic Articles
Special Issue 21 (Guest editor: K. Suzuki ) "The 4th International Conference on Maintenance Science and Technology (ICMST-Tohoku 2018)"
AA163	Regular Paper pp.112-117
	Application of Ice Plug Technology to Nitric Acid Pipe Systems	Daiki OSANAI et al.
AA164	Regular Paper pp.118-123
	Investigating the performances of parameters of magnetic hysteretic loop on characterizing the residual plastic strain in low carbon steel	Xiucheng LIU et al.
New Technology
NT95	Classification :3 - C	Dev. Level: Phase 3
	Development of Decision Making Support Tool for BWR Containment Venting under Severe Accident	TEPCO SYSTEMS CORPORATION (TEPSYS), TOKYO ELECTRIC POWER COMPANY HOLDINGS (TEPCO HD)


Vol.11 No.2 (September, 2019)
Academic Articles
AA157	Regular Paper pp.65-78
	Evaluation of Capabilities on Ultrasonic Testing Examiners Using Probability of Defect Detection and Cumulative Failure Probability	Masayoshi KOJIMA et al.

Special Issue 20 (Guest editor: K. Suzuki ) "The 4th International Conference on Maintenance Science and Technology (ICMST-Tohoku 2018)"
AA158	Regular Paper pp.79-85
	Numerical Investigation on Persistence of Modified Residual Stresses Due to Shot Peening	Kazuki IKUSHIMA et al.
AA159	Regular Paper pp.86-91
	Operation and Maintenance experience of Sodium Leak Detector in Monju	Keitaro MUTO et al.
AA160	Regular Paper pp.92-98
	Relationship between frequency characteristic of turbulent velocity fluctuation and wall thinning rate by flow-accelerated corrosion	Tatsuru KANEKO et al.
AA161	Regular Paper pp.99-105
	3D Environment Reconstruction Based on Images Obtained by Reconnaissance Task in Fukushima Daiichi Nuclear Power Station	Toshihide HANARI et al.
AA162	Regular Paper pp.106-111
	Material research on RPV in decommissioning Hamaoka unit-1 (Progress report)	Hideki YUYA et al.
New Technology
NT94	Classification :6 - C	Dev. Level: Phase 1
	Development of a Maintenance Support Tool Using Augmented Reality Technology	Toshiba Energy Systems & Solutions Corporation


Vol.11 No.1 (May, 2019)
Academic Articles
Special Issue 19 (Guest editor: K. Suzuki ) "The 4th International Conference on Maintenance Science and Technology (ICMST-Tohoku 2018)"
AA150	Regular Paper pp.1-7
	Eddy Current Testing System for Heat Affected Zone of In-Core Monitor Housing Inner Surface	Noriyasu KOBAYASHI et al.
AA151	Regular Paper pp.8-15
	Development of Reliability Assessment Model for Seismic Loading that considers Fatigue Damage	Masayuki KAMAYA et al.
AA152	Regular Paper pp.16-26
	Hammering inspection using AE sensor for embedded hardware	Kouzou HATTORI et al.
AA153	Regular Paper pp.27-33
	Social infrastructural diagnosis by hammering inspection with AE sensor	Yoshihiro ISOBE et al.
AA154	Regular Paper pp.34-39
	TEPCO’s Work Management Initiatives	Hidenori SATO et al.
AA155	Regular Paper pp.40-45
	Research on hydrogen safety technology utilizing the automotive catalyst	Hirohisa TANAKA et al.

AA156	Regular Paper pp.46-64
	X-band electron LINAC-based compact neutron source for nuclear debris on-site screening using short-distance neutron resonance transmission analysis	Yudhitya KUSUMAWATI et al.
New Technology
NT93	Classification :7 - C	Dev. Level: Phase 1
	Manipulator Pose Estimation System Using Stereo Camera for Decommissioning Work	Hitachi-GE Nuclear Energy, Ltd. Hitachi, Ltd.


Vol.10 No.4 (February, 2019)
Academic Articles
AA149	Regular Paper pp.9-17
	Intergranular Strains of Plastically Deformed Austenitic Stainless Steel	Kenji SUZUKI et al.
New Technology
NT92	Classification :7 - A	Dev. Level: Phase 3
	The first FSD due to the measures associated with PWR including SG contains nickel base alloy materials (Inconel 690)	Mitsubishi Heavy Industries, LTD. Nuclear Plant Service Engineering co. ,Ltd.

Vol.10 No.3 (November, 2018)
New Technology
NT91	Classification :6 - C	Dev. Level: Phase 1
	Development of a MAV Equipped with Rotatable Attachment Mechanism for Movable Observation System	Hitachi-GE Nuclear Energy, Ltd. Hitachi, Ltd.

Vol.10 No.2 (August, 2018)
Academic Articles
AA148	Regular Paper pp.1-8
	A consideration on the use of shear waves to improve the sensitivity of an optical ultrasonic sensor for under-sodium viewers	Koichi SARUTA et al.
New Technology
NT90	Classification :1 - C	Dev. Level: Phase 3
	Development of a Virtual Ultrasonic Testing System	Mitsubishi Heavy Industries, LTD.

Vol.10 No.1 (May, 2018)
New Technology
NT89	Classification :7- C	Dev. Level: Phase 2
	Development of a power-saving and wireless radiation-monitoring system	Toshiba Power Systems Radiation Techno-Service Co., LTD. Toshiba Energy Systems & Solutions Corporation

Vol.9 No.4 (March, 2018)
New Technology
NT88	Classification :6 - A	Dev. Level: Phase 3
	Utilizing Examples of 3D Laser Scanning Techniques (The updated version)	Mitsubishi Heavy Industries, Ltd. (MHI) Nuclear Plant Service Engineering Co., Ltd. (NUSEC)

Vol.9 No.3 (November, 2017)
Academic Articles
Special Issue 18 (Guest editor: Z. Chen) "The 3rd International Conference on Maintenance Science and Technology (ICMST-Shenzhen 2016)"
AA143	Regular Paper pp.152-163
	LCF and HCF of Austenitic Stainless Steels – ND-Monitoring of Physical Properties to predict the SN Curve due to The PHYBAL Procedure for Lifetime Determination	Gerd DOBMANN
AA144	Regular Paper pp.164-167
	Study on Material Properties of Concrete Structures Exposed to Extremely High Temperature due to Severe Accident	Yuma Sato et al.
AA145	Regular Paper pp.168-172
	Toward Effective Nuclear Power Plant Ageing Management - On the Second Revision of the AESJ Code -	Masahide Suzuki et al.
AA146	Regular Paper pp.173-184
	Development of Ultrasonic Inspection for Main Coolant Line Welds in EPR Nuclear Power Plant	Huaidong CHEN et al.
AA147	Regular Paper pp.185-190
	The glass coated composite pipe applied in nuclear power plants	Shuangxi WANG et al.
New Technology
NT86	Classification :3 - C	Dev. Level: Phase 2
	Development of Desktop Plant Simulator to Treat Simultaneous Accident Progress in Reactor and Spent fuel pool	TEPCO SYSTEMS CORPORATION (TEPSYS)
NT87	Classification :3 - C	Dev. Level: Phase 1
	Prediction method of improved residual stress distribution by shot peening using large scale analysis method	Kazuki Ikushima et al.

Vol.9 No.2 (August, 2017)
Academic Articles
Special Issue 17 (Guest editor: Z. Chen) "The 3rd International Conference on Maintenance Science and Technology (ICMST-Shenzhen 2016)"
AA125	Regular Paper pp.33-37
	Training for a wider application of atom probe tomography in reactor ageing management	Dongyue CHEN et al.
AA126	Regular Paper pp.38-43
	A Solution of Atom Map Data Analysis for Atom Probe Tomography Training	Dongyue CHEN et al.
AA127	Regular Paper pp.44-51
	Ultrasonic Guided Wave Approach for Inspecting Concave Surface of the Laser Butt-welded Pipe	Akinori FURUSAWA et al.
AA128	Regular Paper pp.52-59
	Thermal Management of Heat Resistant FBG Sensing for High Temperature Industrial Plants	Akihiko NISHIMURA et al.
AA129	Regular Paper pp.60-65
	R&D of Multi-Frequency ECT Algorithms for FBR SG Tubes	Ovidiu MIHALACHE et al.
AA130	Regular Paper pp.66-71
	Insider Malicious Behaviors Detection and Prediction Technology for Nuclear Security	Shi CHEN et al.
AA131	Regular Paper pp.72-77
	Evaluation of Hardening under Ion Irradiation in Reactor Pressure Vessel Model Alloys by Nano-indentation Techniques	Liang CHEN et al.
AA132	Regular Paper pp.78-83
	Quantitative Evaluation of Stress Corrosion Cracking Based on Features of Eddy Current Testing Signals	Li WANG et al.
AA133	Regular Paper pp.84-90
	3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading	Xiaoyong Ruan et al.
AA134	Regular Paper pp.91-96
	Evaluation of environmental compatibility of EHP (extra high purity) using austenitic stainless steel cladding material	Junji Etoh et al.
AA135	Regular Paper pp.97-103
	Effect of Detector Pose Uncertainty in Localization of Radiation Sources	Doyeon KIM et al.
AA136	Regular Paper pp.104-111
	A Research on Numerical Simulation of ACFM Signals for Nondestructive Inspection of Buried Pipes in Nuclear Power Plants	Xudong Li et al.
AA137	Regular Paper pp.112-117
	Safety and Standardization Issues of Nuclear Power Plants in Design and Operation on ISO12100 of Safety Design Principle	Michitsugu Mori
AA138	Regular Paper pp.118-125
	Performance Based Maintenance Concept to Optimize Inspection Schedule	Masayuki KAMAYA
AA139	Regular Paper pp.126-131
	Development of the Remote Decontamination Robot “MHI-MEISTeRⅡ” for an Upper Floor of Reactor Building in Fukushima Daiichi NPP	Leona MORIKAWA et al.
AA140	Regular Paper pp.132-137
	Reactivity Measurement Based on a New Finite-Time Convergent 2-Order Differentiator	Zhe Dong
AA141	Regular Paper pp.138-144
	Why graphite ? A Structural Study from the Atomic to the Macrocsopic scales.	Zhou ZHOU et al.
AA142	Regular Paper pp.145-151
	Treatment of spent radioactive cationic exchange resins used in nuclear power plants by Fenton-like oxidation process	Xu Lejin et al.
New Technology
NT85	Classification :5 - B	Dev. Level: Phase 3
	Water Jet Peening Technology for BWR internals on cracked surface	Hitachi-GE Nuclear Energy, Ltd. The Japan Atomic Power Company

Vol.9 No.1 (May, 2017)
Academic Articles
Special Issue 16 (Guest editor: K. Demachi) "Development of Resilience Evaluation Method for Nuclear Power Plant"
AA122	Regular Paper pp.1-14
	Development of Resilience Evaluation Method for Nuclear Power Plants (Part 3: Study of Evaluation Method and Applicability of Resilience Index)	Masaaki SUZUKI et al.


AA123	Regular Paper pp.15-25
	Effect of Scaly Structure on the Measurement of Pipe Wall Thickness using EMAT	Hongjun SUN et al.
AA124	Regular Paper pp.26-32
	Characterization of the Corroded Surface Morphology of a Carbon Steel Piping Elbow Affected by Flow-Accelerated Corrosion	Hiroshi ABE et al.

New Technology
NT83	Classification :1 - C	Dev. Level: Phase 3
	Monitoring of pipe wall thinning using high-temperature thin-film UT sensor	Mitsubishi Heavy Industries, LTD.
NT84	Classification :5 - A	Dev. Level: Phase 1
	Safety enhancement of fast reactor using nanoparticles suspended sodium and its effect on application	Jun-ichi SAITO, Japan Atomic Energy Agency Kuniaki ARA, Japan Atomic Energy Agency
General Articles
GA21	Severe Weather Data near Nuclear power Station and Reprocessing Fuel Facility in Japan	Tadahisa Nagata

Vol.8 No.4 (February, 2017)
Academic Articles
Special Issue 16 (Guest editor: K. Demachi) "Development of Resilience Evaluation Method for Nuclear Power Plant"
AA121	Regular Paper pp. 57-65
	Development of Resilience Evaluation Method for Nuclear Power Plant (Part 4: Concept of System Safety on Operating Nuclear Power Plant)	Hiroshi MIYANO et al.

New Technology
NT82	Classification :1 - A	Dev. Level: Phase 2
	Development of the Eddy Current Testing (ECT) technique for the Feedwater nozzles of Nuclear Power Plant Reactor Pressure Vessels.	Tokyo Electric Power Company Holdings Inc., Hitachi-GE Nuclear Energy, LTD., Toshiba Corporation


Vol.8 No.3 (November, 2016)
New Technology
NT80	Classification :7 - C	Dev. Level: Phase 2
	High-pressure Water Jet Decontamination Apparatus for Upper Part of 1st Floor of Reactor Buildings for Fukushima Daiichi Nuclear Power Station	Hitachi-GE Nuclear Energy, Ltd.
NT81	Classification :7 - C	Dev. Level: Phase 2
	Demonstration test of vacuuming/blasting decontamination technologies for high position	Mitsubishi Heavy Industries, LTD.


Vol.8 No.2 (August, 2016)
Academic Articles
AA117	Regular Paper pp.13-22
	Building ontology for fire emergency planning and support	Noel Tay Nuo Wi et al.
Special Issue 16 (Guest editor: K. Demachi) "Development of Resilience Evaluation Method for Nuclear Power Plant"
AA118	Regular Paper pp.23-31
	Development of Resilience Evaluation Method for Nuclear Power Plant (Part 1: Proposal of Resilience Index for Assessment of Safety of Nuclear Power Plant under Severe Accident)	Kazuyuki DEMACHI et al.
AA119	Regular Paper pp.32-42
	Development of Resilience Evaluation Method for Nuclear Power Plant (Part 2: Development of Failure Probability Assessment Model for Static Components)	Masayuki KAMAYA et al.

New Technology
NT78	Classification :4 - B,7 - C	Dev. Level: Phase 1
	Quadruped Robots for Nuclear Facilities: Development of Cooperative Carrying and Unloading Functions	TOSHIBA Corporation
NT79	Classification :1 - C	Dev. Level: Phase 1
	Modeling of columnar crystal structure in austenitic weld metal for UT wave propagation simulation	Nondestructive Evaluation Center, Japan Power Engineering and Inspection Corporation Ryoji MIZUNO et al.

Vol.8 No.1 (May, 2016)
General Articles
GA20	The Recent Status of Nuclear Technology Development in Thailand	Sirinart LAOHAROJANAPHAND et al.
Academic Articles
AA116	Regular Paper pp.1-12
	Measurement of Flow Accelerated Corrosion Rate at an Elbow Pipe and Combination Effect of an Upstream Orifice	Yoichi UTANOHARA et al.
New Technology
NT76	Classification :5 - A	Dev. Level: Phase 3
	Development of Remote Decontamination Technologies improving Internal Environment of Reactor Building at Fukushima Daiichi NPS	Masahiro SAITO, et al. (Toshiba Corporation)
NT77	Classification :3 - C	Dev. Level: Phase 2
	Development of the FLEXible radiation DOSE evaluation software (FLEXDOSE)	TEPCO Systems Corporation (TEPSYS)

Vol.7 No.4 (February, 2016)
Academic Articles
AA115	Regular Paper pp.206-215
	POD Evaluation for Joint Angles from Inertial and Optical Motion Capturing System	Kai SHIMIZU et al.
New Technology
NT74	Classification :7 - A	Dev. Level: Phase 2
	Dry Ice Blast Decontamination to In-service equipment in Japanese PWR Plant	Mitsubishi Heavy Industries, LTD.
NT75	Classification :1 - A	Dev. Level: Phase 1
	Effects of metallic diaphragms on sensitivity characteristics of an optical ultrasonic sensor and reduction of interrogation time based on wavelength division multiplexing for under-sodium visual inspection	Koichi Saruta, et al.

Vol.7 No.3 (November, 2015)
Academic Articles
AA114	Regular Paper pp.199-205
	Maintenance Index for System Safety Assessment for Aging Nuclear Power Plant	Kazuyuki Deamachi et al.
New Technology
NT72	Classification :1 - A	Dev. Level: Phase 1
	A New Mechanical Condition-based Maintenance Technology Using Instrumented Indentation Technique	Shigetaka OKANO, et al.
NT73	Classification :7 - C	Dev. Level: Phase 2
	Survey robots for Fukushima Daiichi Nuclear Power Plant	Hitachi-GE Nuclear Energy, Ltd.

Vol.7 No.2 (August, 2015)
Academic Articles
Special Issue 15 (Guest editor: T. Takagi) "The 2nd International Conference on Maintenance Science and Technology (ICMST-Kobe 2014)"
AA106	Regular Paper pp.138-144
	Inventory estimation of ¹³⁷Cs in radioactive wastes generated from contaminated water treatment system in Fukushima Daiichi Nuclear Power Station	Jun KATO et al.
AA107	Regular Paper pp.145-153
	Development of an Augmented Reality Based Simulation System for Cooperative Plant Dismantling Work	Hirotake ISHII et al.
AA108	Regular Paper pp.154-159
	Status of Fukushima Daiichi Decommissioning and Decontamination Project	Douglas M. Chapin
AA109	Regular Paper pp.160-165
	Numerical Evaluation of Material’s Degradation under Various Irradiation Conditions	Toshiki NAKASUJI et al.
AA110	Regular Paper pp.166-171
	Fracture Toughness Curves of Japanese Reactor Pressure Vessel Steels considering Neutron Irradiation Embrittlement	Kentaro YOSHIMOTO et al.
AA111	Regular Paper pp.172-178
	Non-Destructive Evaluation of Multiple-site Small Cracks in Low Cycle Fatigue of Austenitic Stainless Steel by Four-point Probe DC Potential Difference Method	Shio NAKANISHI et al.

AA112	Regular Paper pp.179-188
	Equivalent current models and the analysis of directional ECT signals	Weiying CHENG
AA113	Regular Paper pp.189-198
	Sustainability of compressive residual stress by stress improvement processes	Satoru NISHIKAWA et al.
New Technology
NT71	Classification :5 - B	Dev. Level: Phase 3
	Application of TiO₂ injection technology for BWR plants to mitigate SCC susceptibility of core internals	Tokyo Electric Power Company and TOSHIBA Corporation

Vol.7 No.1 (May, 2015)
Academic Articles
Special Issue 14 (Guest editor: T. Takagi) "The 2nd International Conference on Maintenance Science and Technology (ICMST-Kobe 2014)"
AA87	Regular Paper pp.1-7
	Development and Applicability Evaluation of Frequency Response Function of Structures to Fluctuation	Kohei SODA et al.
AA88	Regular Paper pp.8-13
	Update on Implementation of Severe Accident Countermeasures in the United States	Ryan VANSTON et al.
AA89	Regular Paper pp.14-19
	Semi-nondestructive Measurement of Weld Residual Stress Distribution in Austenitic Stainless Steel using Indentation Technique without Reference Load under Non-stress State	Daisuke KANAMARU et al.
AA90	Regular Paper pp.20-33
	Determination of the Probability of Failure (POF) in a Sensitivity Study Based on a Probabilistic FAD-Approach and POD-Curves Using PAUT	Gerd DOBMANN et al.
AA91	Regular Paper pp.34-42
	Noble Gas Control Room Accident Filtration System for Severe Accident Conditions (N-CRAFT)	Axel HILL et al.
AA92	Regular Paper pp.43-49
	Fatigue Damage Management Based on Postulated Crack Growth Curve	Masayuki KAMAYA et al.
AA93	Regular Paper pp.50-58
	Correction of Over and Under Exposure Images Using Multiple Lighting System	Jonghoon IM et al.
AA94	Regular Paper pp.59-65
	Developments of Flat ∞ Coil for Defect Searching in the Curved Surfaces	Kouki MARUYAMA et al.
AA95	Regular Paper pp.66-73
	Reconstruction of Grand Design for Fatigue Evaluation based on Fatigue Failure Analysis of Japanese NPPs	Takao NAKAMURA et al.
AA96	Regular Paper pp.74-77
	Ageing Management of Nuclear Power Plants in China	Li Liu et al.
AA97	Regular Paper pp.78-83
	Harmonic Balance Analysis for M agnetic Hysteresis under Static and Dynamic Stresses	Hideaki NEMORI et al.
AA98	Regular Paper pp.84-89
	Development of New Type Passive Autocatalytic Recombiner - Part1. Characterization of Monolithic Catalyst	Yu KAMIJI et al.
AA99	Regular Paper pp.90-95
	The Concept of Passive Cooling Systems for Inherently Safe BWRs	Naoyuki ISHIDA et al.
AA100	Regular Paper pp.96-101
	Semi-Nondestructive Determination of Anisotropic Stress-Strain Curve Using Asymmetric Indenters with Different Vertical Angles	Shigetaka OKANO et al.
AA101	Regular Paper pp.102-107
	A Study on Insulation Degradation in Thermally Aged Ethylene Propylene Rubber Using Volume Resistivity Measurement	Tariq ALSHAKETHEEP et al.
AA102	Regular Paper pp.108-116
	Reliability Based Thermal Fatigue Evaluation Method against Random Fluid Temperature Fluctuations	Masaaki SUZUKI et al.
AA103	Regular Paper pp.117-121
	Microstructural Evolution of Thermally Aged RPV Model Alloys by 3D Atom Probe	Li LIU et al.
AA104	Regular Paper pp.122-128
	Development of New Type Passive Autocatalytic Recombiner - Part2. Proposal of Conceptual Structure	Shingo HIRATA et al.
AA105	Regular Paper pp.129-137
	Statistical Model of Micro Crack Growth for the Evaluation of Accumulated Fatigue in NPPs	Shigeki ABE et al.
New Technology
NT69	Classification :7 - C	Dev. Level: Phase 2
	MHI-Teleoperated Robot for decontamination and concrete core sampling in Fukushima daiichi reactor buildings	Mitsubishi Heavy Industries, LTD.
NT70	Classification :5 - A	Dev. Level: Phase 1
	Flow-Induced Vibration Suppression of Jet Pump in Boiling Water Reactor	TOSHIBA Corporation

Vol.6 No.4 (Feb, 2015)
Academic Articles
AA82	Technical Note pp.107-117
	Main Factors for Fatigue Failure Probability of Pipes Subjected to Fluid Thermal Fluctuation	Hideo MACHIDA et al.
Special Issue 13 (Guest editor: Y. Sakakibara) "Research on Ageing Management of Nuclear Power Plant for Safe Long-Term Operating Using Serviced Structural Materials through Decommissioning"
AA83	Review Paper pp.118-130
	A Review of Evaluation Methods Developed for Numerical Simulation of the Temperature Fluctuation Contributing to Thermal Fatigue of a T-junction Pipe	Akira NAKAMURA et al.
AA84	Regular Paper pp.131-145
	Effect of Ethanolamine Injection on Wall Thinning Rate of PWR Carbon Steel Components	Takuya FUKUMURA
AA85	Regular Paper pp.146-152
	Research of Estimation Method of Thermal Aging Embrittlement on Cast Austenitic Stainless Steel	Teruyoshi ABE et al.
AA86	Regular Paper pp.153-164
	Evaluation of Wall Thinning of the Steel Piping after Long Term Operation at Fugen Power Station	Ryosuke ANDO et al.
New Technology
NT67	Classification :2 - A, 2 - B	Dev. Level: Phase 2
	Development of the electric shock prevention transparent cover for infrared thermography diagnosis	The Japan Atomic Power Company
NT68	Classification :7 - C	Dev. Level: Phase 2
	High-pressure water decontamination apparatus "Arounder"	Hitachi-GE Nuclear Energy, Ltd.

Vol.6 No.3 (Nov, 2014)
Academic Articles
Special Issue 12 (Guest editor: A. Gofuku) "Hybrid-type Agent System to Diagnose Small Disturbances of Plants"
AA78	Regular Paper pp.48-56
	Integration Technique of Diagnostic Results in Hybrid-type Agent System	Akio GOFUKU et al.
AA79	Regular Paper pp.57-70
	Plant Transients under Small Abnormalities of FBR “Monju” Calculated by a Plant System Code	Hiroyasu MOCHIZUKI
AA80	Regular Paper pp.71-85
	Diagnostic Agent using Parasitic Discrete Wavelet Transform for the Hybrid Diagnostic Agent System for the Fast-breeder Reactor “Monju”	Takashi NAGAMATSU et al.
AA81	Regular Paper pp.86-106
	Process Signal Selection Method to Improve the Impact Mitigation of Sensor Broken for Diagnosis Using Machine Learning	Hirotsugu MINOWA et al.
New Technology
NT66	Classification :3 - C	Dev. Level: Phase 3
	Development of the Air dose Rate Evaluation System (ARES)	TEPCO Systems Corporation (TEPSYS)

Vol.6 No.2 (August, 2014)
Academic Articles
AA77	Regular Paper pp.34-47
	Hardness Prediction of HAZ in Temper Bead Welding by Non-Consistent Layer Technique	Lina YU et al.
New Technology
NT65	Classification :1 - A	Dev. Level: Phase 3
	Blockage Monitoring Method of SG Tube Support Plate with Intelligent ECT	Mitsubishi Heavy Industries, LTD.

Vol.6 No.1 (May, 2014)
Academic Articles
AA74	Regular Paper pp.1-13
	Study of the Optimization of Maintenance Plan for Nuclear Power Plants	Takayuki AOKI et al.
Special Issue 11 (Guest editor: N. Kasahara) "High Cycle Thermal Fatigue Induced by Fluid Temperature Fluctuation"
AA75	Regular Paper pp.14-23
	Development of Thermal Fatigue Evaluation Methods of Piping Systems	Naoto KASAHARA et al.
AA76	Regular Paper pp.24-32
	Effect of Thermo-Mechanical Loading Histories on Fatigue Crack Growth Behavior and the Threshold in SUS 316 and SCM 440 Steels -For prevention of high cycle thermal fatigue failures-	Masakazu OKAZAKI et al.

Errata	Errata p.33
	ERRATUM for “Theoretical Investigation of Oxidation Mechanism of Fuel Cladding in Light-Water Reactor”, from EJAM, Vol. 5, No. 1, pp. 1-16
New Technology
NT63	Classification :4 - B, 5 - B	Dev. Level: Phase 2
	Double-arm Heavy Machinery-type Robot "ASTACO-SoRa"	Hitachi-GE Nuclear Energy, Ltd.
NT64	Classification :1 - B, 4 - B	Dev. Level: Phase 3
	Quadruped Robot for Nuclear Facilities	TOSHIBA Corporation

Vol.5 No.4 (Feb, 2014)
Academic Articles
AA72	Regular Paper pp.201-227
	Visualization and Quantitative Evaluation of Stress Corrosion Cracking Using the Three-Dimensional Phased Array Ultrasonic Technique	So KITAZAWA et al.
AA73	Regular Paper pp.228-237
	Reliability Assessment for Thickness Inspection of Pipe Wall using Probability of Detection	Hiroyuki NAKAMOTO et al.
New Technology
NT60	Classification :3 - A	Dev. Level: Phase 1
	Development of Future Prediction of Animation by coupling of Principle Component Analysis and Singular Spectrum Analysis	Kazuyuki DEMACHI et al.
NT61	Classification :1 - A, 3 - A	Dev. Level: Phase 1
	Validation of Multifrequency and Window-Multifrequency Techniques using Remote Field Eddy Currents for ISI of FBR Tubes	Ovidiu MIHALACHE et al.
NT62	Classification :1 - A, 4 - A, 6 - A,	Dev. Level: Phase 1
	Remote Controlled Robot with expandable features	Mitsubishi Heavy Industries, Ltd. (MHI)

Vol.5 No.3 (Nov, 2013)
Academic Articles
AA68	Regular Paper (Contributed) pp.155-164
	Online Monitoring of Pipe Wall Thinning by Electromagnetic Acoustic Resonance Method	Ryoichi URAYAMA et al.
Special Issue 10 (Guest editor: S. Komazaki) "Materials Degradation and Damage in Nuclear Power Plant"
AA69	Regular Paper pp.165-174
	Relationship between Duplex Grain Structure and Grain-boundary Precipitates in Ni2M-stabilized Alloy	Toshiaki HORIUCHI et al.
AA70	Regular Paper pp.175-184
	Influence of Hydrogen in Steel on Oxidation Behavior of Low Carbon Austenitic Stainless Steel in High Temperature Water	Motoki NAKAJIMA et al.
AA71	Regular Paper pp.185-200
	Observation of Fatigue Crack Initiation and Growth in Stainless Steel to Quantify Low-Cycle Fatigue Damage for Plant Maintenance	Masayuki KAMAYA et al.
New Technology
NT58	Classification :1 - A	Dev. Level: Phase 2
	Electro-Magnetic Induction Testing for Inspection of Wall Thickness and Inner-surface Defects- “i Eddy” System -	Dainichi Machine & Engineering Co., Ltd.
NT59	Classification :1 - A	Dev. Level: Phase 1
	The Advanced lining inspection technology for seawater piping	Mitsubishi Heavy Industries, Ltd. (MHI)

Vol.5 No.2 (Aug, 2013)
Academic Articles
Special Issue 9 (Guest editor: T. TAKAGI) "The 1st International Conference on Maintenance Science and Technology for Nuclear Power Plants(ICMST-Tokyo 2012)"
AA59	Regular Paper pp.85-92
	Study on the Structural Integrity of RPV Using PFM Analysis Concerning Inhomogeneity of the Heat-Affected Zone	Koichi MASAKI et al.
AA60	Regular Paper pp.93-100
	Commissioning of portable 950 keV/3.95MeV X-band linac X-ray sources for on-site transmission testing	Mitsuru Ueaska et al.
AA61	Regular Paper pp.101-112
	Determination of High-Risk Zones for Local Wall Thinning due to Flow-Accelerated Corrosion	Shunsuke UCHIDA et al.
AA62	Regular Paper pp.113-120
	On the Efficiency of Direct Sparse Solver for FEM-ECT Analysis	Shigeru HEMMI et al.
AA63	Regular Paper pp.121-127
	Partial CT and Structural Analysis with 950 Kev/3.95 Mev X-Band Linac X-Ray Sources	Wenjing Wu et al.
AA64	Regular Paper pp.128-131
	Silicon Carbide TRIPLEXTM Fuel Clad and SiC Channel Boxes for Accident Resistance and Durability	Herbert FEINROTH.
AA65	Regular Paper pp.132-137
	Safety Measures for the Main Control Board Replacement Project at Ikata Units 1 & 2	Nozomu HASHIMOTO et al.
AA66	Regular Paper pp.138-145
	Revising Scenario Map for Plant Management via Interaction of Stakeholders’ Intentions and Constraints	Yukio OHSAWA et al.

AA67	Regular Paper pp.146-154
	Basic Study on the Phased Array UT Technique for Crack Depth Sizing in Ni-Based Alloy Weld	Taiji HIRASAWA et al.
New Technology
NT56	Classification :1 - A	Dev. Level: Phase 1
	A New Method of Eddy Current Testing Insensitive to Defect Orientation	TOSHIBA Corporation
NT57	Classification :2 - B	Dev. Level: Phase 1
	Remote Control Monitoring Robot System in Large-Scale Disaster Scenes	Hitachi-GE Nuclear Energy, Ltd.

Vol.5 No.1 (May, 2013)
Academic Articles
Special Issue 8 (Guest editor: T. TAKAGI) "The 1st International Conference on Maintenance Science and Technology for Nuclear Power Plants(ICMST-Tokyo 2012)"
AA49	Regular Paper pp.1-6
	Theoretical Investigation of Oxidation Mechanism of Fuel Cladding in Light-Water Reactor	Yasunori YAMAMOTO et al.
AA50	Regular Paper pp.7-14
	Nondestructive Detection of Local Material Thinning in Ferromagnetic Materials by Magnetic Adaptive Testing	Gábor VÉRTESY et al.
AA51	Regular Paper pp.15-24
	R&D to lifetime management – ND-characterization of ageing phenomena	Gerd DOBMANN et al.
AA52	Regular Paper pp.25-33
	Implementation of electromagnetic acoustic resonance in pipe inspection	Ryouichi URAYAMA et al.
AA53	Regular Paper pp.34-41
	Experimental Study of Influence of Elbow Curvature on a Swirling Flow Generated in a Three-Dimensionally Connected Dual Elbow	Tatsuya KUBO et al.
AA54	Regular Paper pp.42-50
	Simplified Electromagnetic Inverse Analysis Technique about the Inclined Defect for Welded Zone of High Chromium Steel	Shogo NAKASUMI et al.
AA55	Regular Paper pp.51-61
	Novel Mode Decomposition Algorithms for Lamb Wave Signal Analysis in Online Monitoring of Structures	Oleksii KARPENKO et al.
AA56	Regular Paper pp.62-69
	Standardized Procedure for Tsunami PRA by AESJ	Yukihiro KIRIMOTO et al.
AA57	Regular Paper pp.70-76
	LWR Sustainability: Assessment of Aging of Nuclear Power Plant Safety Related Concrete Structures	Herman L. Graves, III et al.
AA58	Regular Paper pp.77-84
	Durability Evaluation Method on Rebar Corrosion of Reinforced Concrete	Yoshinori KITSUTAKA
New Technology
NT53	Classification :5 - B	Dev. Level: Phase 3
	Effectiveness of Oxygen Treatment on FAC Mitigation in PWR Secondary System	The Japan Atomic Power Company (JAPC)
NT54	Classification :1 - A:4 - A	Dev. Level: Phase 3
	Robot Technologies of PWR for Nuclear Power Plant Maintenance	Mitsubishi Heavy Industries, Ltd. (MHI)
NT55	Classification :1 - A	Dev. Level: Phase 3
	Phased Array Ultrasonic Testing for Components with complex surface geometry	TOSHIBA Corporation

Vol.4 No.4 (Feb, 2013)
Academic Articles
Special Issue 7 (Guest editor: I. KOMURA) "Recent Situation of Performance Demonstration (PD) Program Europe, Asia, and USA."
AA46	Regular Paper (Invited) pp.116-124
	Inspection Qualification and Implementation of ENIQ in Sweden	Tommy Zettervall.
AA47	Regular Paper (Invited) pp.125-132
	Trends Identified Between Successful and Unsuccessful Candidates that have Participated in the Japanese Performance Demonstration (PD) Program of Stress Corrosion Cracking (SCC) Depth Sizing	Hajime SHOHJI et al.
AA48	Regular Paper (Invited) pp.133-141
	Current Status of Ultrasonic Examination Performance Demonstration in Korea	Yongsik KIM et al.
New Technology
NT50	Classification :1 - A	Dev. Level: Phase 3
	Development of Smart Array ECT System for the Inspection of Steam Generator tubes	The Kansai Electric Power Co., Inc. (KEPCO) Nuclear Engineering, Ltd. (NEL)
NT51	Classification :3 - A	Dev. Level: Phase 1
	Pt Deposition Treatment Combined with Chemical Decontamination	Hitachi-GE Nuclear Energy, Ltd. (HGNE) Hitachi Research Laboratory, Hitachi, Ltd. (HRL) GE-Hitachi Nuclear Energy America, LLC (GEH)
NT52	Classification :1 - A	Dev. Level: Phase 3 Dev. Level: Phase 1
	Application of eddy current testing for vessel and in-vessel components	TOSHIBA Corporation

Vol.4 No.3 (Nov, 2012)
Academic Articles
AA45	Regular Paper (Invited) pp.105-115
	Considerations for Statistical Analysis of Nondestructive Evaluation Data: Hit/Miss Analysis	Jeremy KNOPP et al.
New Technology
NT48	Classification :3 - A	Dev. Level: Phase 3
	BWR Reload Core Loading Pattern Optimization System FINELOAD-3^TM	TEPCO Systems Corporation (TEPSYS)
NT49	Classification :5 - A	Dev. Level: Phase 3
	Advanced INLAY System for Reactor Vessel of PWR	Mitsubishi Heavy Industries, Ltd. (MHI)

Vol.4 No.2 (Aug, 2012)
Academic Articles
AA39	Regular Paper (Contributed) pp.36-56
	Proactive Material Degradation Research Subjects for Light Water Reactors	Tetsuo SHOJI et al.
AA40	Regular Paper (Contributed) pp.57-67
	Fabrication of Micro Capsule Containing Fluorescent Magnetic Particles for Advanced Inspection of Heat Exchanger Tubes	Fuyumi ITO et al.
Special Issue 6 (Guest editor: Y. WATANABE / T.UCHIMOTO) "Understanding and Managing Pipe Wall Thinning"
AA41	Regular Paper (Invited) pp.63-78
	The Role of Flow in Flow-Accelerated Corrosion under Nuclear Power Plant Conditions	John M. PIETRALIK.
AA42	Regular Paper (Invited) pp.79-87
	Critical Consideration on Wall Thinning Rate by Liquid Droplet Impingement Erosion	Nobuyuki FUJISAWA et al.
AA43	Regular Paper (Invited) pp.88-95
	Method for Thinning Shape Evaluation of Elbow due to LDI and Representative Thinning Shape for Seismic Evaluation of Eroded Elbow	Ryo MORITA et al.
AA44	Regular Paper (Invited) pp.96-104
	Nondestructive Investigation of Wall Thinning in Doubled Layer Tube by Magnetic Adaptive Testing	Gábor VÉRTESY et al.
New Technology
NT46	Classification :2 - B	Dev. Level: Phase 3
	The Application of Signal Analysis to Condition Monitoring and Plant Diagnosis of Commercial Nuclear Power Plant	TEPCO Systems Corporation (TEPSYS)
NT47	Classification :6 - A	Dev. Level: Phase 3
	Utilization examples of 3D Laser Scanning Technique	Mitsubishi Heavy Industries, Ltd. (MHI) Nuclear Plant Service Engineering Co., Ltd. (NUSEC)

Vol.4 No.1 (May, 2012)
Academic Articles
AA37	Regular Paper pp.1-21
	Study on the Ultrasound Propagation in Cast Austenitic Stainless Steel	Kazunobu SAKAMOTO et al
AA38	Regular Paper pp.22-35
	Capability of Ultrasonic Testing for Cast Austenitic Stainless Steel in Japanese Pressurized Water Reactors	Kazunobu SAKAMOTO et al
New Technology
NT44	Classification :5 - A	Dev. Level: Phase 3
	Cleaning the secondary side of steam generators of Tomari Power Station Unit 1/2 using ASCA and UEC technology	Mashiho Suzuki and Eiji Oohashi Mechanical Maintenance and Engineering Section Tomari Power Station, Hokkaido Electric Power Co., Inc. Japan
NT45	Classification :5 - A	Dev. Level: Phase 3
	Development and Actual Application of Remote-type Vacuum Blast Decontamination　Device	Mitsubishi Heavy Industries, Ltd. (MHI) Nuclear Plant Service Engineering Co., Ltd. (NUSEC)

GA19 (April, 2012)
General Articles
GA19	An International View of the Fukushima Accident, Japanese Response, Japan’s Post Accident Situation and Needed Actions	Douglas M. Chapin

Vol.3 No.4 (Feburary, 2012)
New Technology
NT41	Classification :3 - A	Dev. Level: Phase 1
	Simplified Evaluation Method of Strain Rate Being Generated on Structural Materials during Plant Start-up	The Japan Atomic Power Company Tepco Systems Corporation
NT42	Classification :1 - B	Dev. Level: Phase 2
	ECT system for in-vessel components of nuclear reactor	Hitachi-GE Nuclear Energy, Ltd.
NT43	Classification: 4 - A	Dev. Level: Phase 2
	Underwater Laser Beam Welding Technology for Reactor Vessel	TOSHIBA Corporation.

Vol.3 No.3 (November, 2011)
General Articles
GA18	Current Status and Outlook of the Wind Energy in China	Hideo KUBOTA
Academic Articles
AA36	Review Paper pp.92-101
	Simulation and visualization of guided wave propagation by large-scale 3D FEM	Takashi FURUKAWA and Ichiro KOMURA
New Technology
NT39	Classification: 5 - A	Dev. Level: Phase 3
	Metal Surface Stress Improvement by Mechanical Polishing for Preventing Stress Corrosion Cracking	Hitachi-GE Nuclear Energy, Ltd.
NT40	Classification: 1 - B Dev. Level: Phase 2
	Development of UT Sizing Technique of Cracks for Ni Alloy Welding	The Kansai Electric Power Co. Inc. Mitsubishi Heavy Industries, LTD.

Vol.3 No.2 (August, 2011)
General Articles
GA17	A test facility employing a magnetic bearing for mechanical element tests	S. Hirano, K. NISHIYAMA, and K. SUGIYAMA
Academic Articles
AA34	Review Paper pp.54-77
	Computational Challenges in Numerical Simulations of ISI of Ferritic Steam Generator Tubes in Fast Breeder Reactors using Eddy Currents and Multi-frequency Algorithms	Ovidiu MIHALACHE et al.
AA35	Regular Paper (Contributed) pp.78-91
	ANALYSIS OF HYDRAULIC BEARING EFFECT FOR ANTI-VIBRATION BEARING OF VERTICAL-SHAFT PUMP	Hiroshi Miyano et al.
New Technology
NT36	Classification ③	Dev. Level: Stage 3
	Transformer Condition Monitoring Diagnostic Technologies to Detect Deterioration and Faults	The Kansai Electric Power Co., Inc.and Mitsubishi Electric Co.
NT37	Classification: 3 - A Dev. Level: Phase 1
	Strain Rate Evaluation of some Typical Nuclear Power Plant Components during Plant Operation	The Japan Atomic Power Company, and Tepco Systems Corporation
NT38	Classification: 1 - B Dev. Level: Phase 3
	Confirmation test of IHSI for pipes with crack	Toshiba Corporation, Takao SASAYAMA, and IHI Corporation, Satoshi HONGO

Vol.3 No.1 (May, 2011)
General Articles
GA16	Maintenance Decision Support Project	Ron Jenkins, Murray Wiseman, and Daming Lin
Academic Articles
AA30	Regular Paper (Contributed) pp.1-10
	Evaluation of Defect Shape Based on Inverse Analysis Considering the Resolution of Magnetic Sensor	Shogo NAKASUMI et al.
Special Issue 5 (Guest editor: I. Komura) "The simulation technique for accelerating the development of NDE technique."
AA31	Regular Paper (Invited) pp.11-24
	Simulation of Ultrasonic Fields and Echoes Obtained Using Angle Beam Transducer by Hybrid FDTD Method	Tomonori KIMURA et al.
AA32	Regular Paper (Invited) pp.25-38
	A Simulation Technique of Non-Destructive Testing using Magneto-Optical Film	Huy Minh LE et al.
AA33	Regular Paper (Invited) pp.39-53
	Detection and sizing of cracks using potential drop techniques based on electromagnetic induction	Yasumoto SATO et al.
New Technology
NT33	Classification: 5 - A (Performance improvement)	Dev. Level: Phase 1
	Evaluation of High Flow Rate Condensate Polisher for Next PWR Plants	Kyushu Electric Power Co., Inc. Organo Corporation
NT34	Classification: 1 - A (Non-destruction examination of metallographic structure) Dev. Level: Phase 2
	DEVELOPMENT OF UNDERWATER REMOTE MICROSCOPIC OBSERVATION TECHNIQUE FOR NUCLEAR REACTOR CORE INTERNALS	Hitachi-GE Nuclear Energy, Ltd. (HGNE)
NT35	Classification: 5 - A (Evaluation technology for IASCC) or 6 - A(Others) Dev. Level: Phase 2
	Application of Tungsten Ball Filling Type Radiation Shielding System to the Pressurizer	Mitsubishi Heavy Industries, Ltd. (MHI) Nuclear Plant Service Engineering Co., Ltd. (NUSEC)

Vol.2 No.4 (February, 2011)
General Articles
GA15	[Special Issue] Maintenance Activities for Alloy 600 in PWR Plants <Part 3>	S. Hirano, K. Hamasaki, and K. Okimura
Academic Articles
AA25	Regular Paper (Contributed) pp.160-167
	Numerical Simulation of Residual Stress Measurement with Acoustic Wave	Cuixiang PEII et al.
AA26	Regular Paper (Contributed) pp.168-180
	Electromagnetic modeling of stress corrosion cracks in Inconel weldsr	Haoyu HUANG et al.
Special Issue 4 (Guest editor: M. UESAKA) "Practical and Advanced Methodologies on Condition-based Maintenance Technology"
AA27	Regular Paper (Invited) pp.181-190
	Efficient Transduction of Circumferential Lamb Waves by a Pair of Line Focus Type Noncontact Air-coupled Ultrasonic Transducers and its Application for Accurate Measurement of Pipe Wall Thickness	Hideo NISHINO et al.
AA28	Regular Paper (Invited) pp.191-199
	Strain Monitoring and Defect Detection in Welded Joints by Using Fiber-Optic Distributed Sensors with High Spatial Resolution	Hideaki MURAYAMA et al.
AA29	Regular Paper (Invited) pp.200-206
	Future Bearing Inspection System using Portable Linac X-ray Source	Tomohiko YAMAMOTO et al.
New Technology
NT29	Classification: 2 - A (Inspection Technology of Valve) Dev. Level: Phase 2
	Condition-Based Maintenance of Motor-Operated Valves in Nuclear Power Plants	Okano Valve MFG. Co.and Tokyo Electrric Power Co. Inc.
NT30	Classification: 4 - A (Maintenance Technology for Replacement of Main Control Boards) Dev. Level: Phase 3
	Replacement Operation Schedule Management of Main Control Boards at Ikata Unit 1&2 Using Full Digital Control Systems	Shikoku Electric Power Co. Inc.
NT31	Classification: 3 - A (Evaluation technology for SCC) Dev. Level: Phase 1
	Current Status of Technical Development of In-pile Tests for IASCC of Irradiated Stainless Steels in JMTR	Japan Atomic Energy Agency
NT32	Classification: 5 - B (Inspection Technology of Valve) Dev. Level: Phase 2
	SCC mitigation method by TiO₂ technique	Tokyo Electric Power Company and TOSHIBA Corporation

Vol.2 No.3 (November, 2010)
General Articles
GA14	[Special Issue] Maintenance Activities for Alloy 600 in PWR Plants <Part 2>	S. Hirano, K. Hamasaki, and K. Okimura
Academic Articles
AA19	Regular Paper (Contributed) pp.82-100
	Environmental Fatigue Evaluation in PLM Activities of PWR plant	Takao NAKAMURA et al.
AA20	Regular Paper (Contributed) pp.101-109
	Remote Detection and Quantitative Evaluation of Wall Thinning Volumes in a Metal Pipe	Linsheng LIU
Special Issue 3 (Guest editor: T. Sawaragi) "Human and Organizational Issues for Interoperable Maintenance and Safety Management: Simulation-Based and Knowledge-Intensive Approaches"
AA21	Regular Paper (Invited) pp.110-119
	A Study for the Practical Methods and Evaluations for the On-Line Maintenance	Naoki CHIGUSA et al.
AA22	Regular Paper (Invited) pp.120-134
	Building Interoperable System Enabling Failure Information Knowledge Sharing between Designing/Manufacturing and Maintenance Departments Focusing on Information Architecture Differences	Akira NAKAJIMA et al.
AA23	Regular Paper (Invited) pp.135-148
	An activity theory-based approach for industrial trouble analysis and its application to similarity evaluation beyond the superficial resemblance	Hiroshi NARAZAKI et al.
AA24	Regular Paper (Invited) pp.149-159
	A Prediction Market Approach to Facilitating Consensus Building among Supply Chain Partners	Hajime MIZUYAMA et al.
New Technology
NT26	Classification: 5 - B (Improvement of degradation mode) Dev. Level: Phase 2
	Outer Surface Irradiated Laser Stress Improvement Process (L-SIP) Applied To Pressurizer as Residual Stress Improvement Method	Mitsubishi Heavy Industries, Ltd. The Japan Atomic Power Company
NT27	Classification: 1 - B (Maintenance Technology for Replacement of Main Control Boards) Dev. Level: Phase 1
	Remotely Operated Inspection Device for BWR Jet Pump	TOSHIBA Corporation
NT28	Classification: 3 - B (Evaluation technology for SCC) Dev. Level: Phase 3
	Review on Conservatism of Guideline for Inspection and Evaluation to BWR internals	Tokyo Electric Power Co, Inc. TOSHIBA Corporation Hitachi-GE Nuclear Energy, Ltd.

Vol.2 No.2 (August, 2010)
General Articles
GA13	[Special Issue] Maintenance Activities for Alloy 600 in PWR Plants <Part 1>	S. Hirano, K. Hamasaki, and K. Okimura
Academic Articles
AA15	Regular Paper (Contributed) pp.43-49
	Electromagnetic Nondestructive Evaluation Method for Discriminating and Sizing of Defects in Bearings	Shingo MAWATARI et al.
Special Issue 2 (Guest editor: M. Mochizuki) "Scientific Approach to Preventive/Proactive Maintenance and Repair Techniques"
AA16	Regular Paper (Invited) pp.50-64
	Evaluation of Weld Residual Stress near the Cladding and J-weld in Reactor Pressure Vessel Head for the assessment of PWSCC Behavior	Jinya KATSUYAMA et al.
AA17	Regular Paper (Invited) pp.65-76
	Effects of Dissolved Hydrogen Content in PWR Primary Water on PWSCC Initiation Property	Koji DOZAKI et al.
AA18	Regular Paper (Invited) pp.77-81
	Inspection, Evaluation and Maintenance Guidelines for Reactor Vessel Internals in JAPAN	Akihiro SAKASHITA et al.
New Technology
NT23	I: Inspection
	Ultrasonic integrity assessment for foundation bolts of nuclear power plants	Hitachi, Ltd. Hitachi-GE Nuclear Energy, Ltd. The Tokyo Electric Power Co, Inc.
NT24	I: Inspection
	Development of the advanced phased array UT technique for accurate sizing of cracks in the nozzle welding	Mitsubishi Heavy Industries, LTD.
NT25	I: Inspection
	Visualization Method of UT Wave Propagation Phenomena for Assisting the Better Understanding of Inspection Results	Japan Power Engineering and Inspection Corporation (JAPEIC)

Vol.2 No.1 (May, 2010)
General Articles
GA11	Activities on Public Awareness of a Prototype Fast Breeder Reactor, Monju, and Casebook of Potential Troubles	T. Yanagisawa, H. Tabata, and M. Mori
GA12	The Current Status of Chinese Nuclear Power Industry and Its Future	Daogang Lu
Academic Articles
Special Issue 1 (Guest editor: F. Inada) "The Technology of Pipe-wall-thinning Management"
AA11	Invited pp.1-13
	Pipe wall thinning management at Electricité de France (EDF)	Thomas KNOOK et al.
AA12	Invited pp.14-24
	A Review: Japanese Pipe Wall Thinning Management Based on JSME Rules and Recent R&D Studies Performed to Enhance the Rules	Isoharu NISHIGUCHI et al.
AA13	Invited pp.25-33
	Quantitative Evaluation of Pipe Wall Thinning by Electromagnetic Acoustic Resonance	Akihiro SAKASHITA et al.
AA14	Invited pp.34-42
	Monitoring System for Pipe Wall Thinning Management using Electromagnetic Acoustic Transducer	Daigo KOSAKA et al.
New Technology
NT19	II: Repair
	INLAY Method Using the Cylindrical Container for Reactor Vessel of PWR	The Kansai Electric Power Co., inc. Mitsubishi Heavy Industries, Ltd.
NT20	IV: Preventive Maintenance
	"WearMATE" Portable Ferrograph Analyzer for Wear Debris Diagnosis	Tokyo Electric Power Co., Inc. TRIBOTEX Co., Ltd.
NT21	IV: Preventive Maintenance
	A New Fiber-optic Multipoint Sensing System for Condition-Based Maintenance	TOSHIBA Corporation
NT22	I: Inspection
	A Monitoring System for Condition-based Maintenance without Laying New Communication Cables	TOSHIBA Corporation

Vol1. No.4 (February, 2010)
General Articles
GA8	Standards (rules) for Incident Informing and Public Notification, and its Procedures for Higashidoori Nuclear Power Station (NPS)	Tsunehiro TADA
GA9	Regarding the "Casebook of Troubles At Rokkasho Reprocessing Plant"	H. AOYAGI & T. KIMURA
GA10	Industry’s Efforts toward Technology Development Related to Aging Management of PWR Plants	Hideo TANAKA
Academic Articles
AA10	Invited pp.99-108
	Computational Methods in Nondestructive Evaluation: A Revolution in Maintenance	Jeremy KNOPP, et al.
New Technology
NT14	V: Others (Operation Management)
	Mitigation for Flow Accelerated Corrosion by Oxygenated Water Chemistry (OWC) in PWR Secondary Cooling System	The Japan Atomic Power Company (JAPC)
NT15	V: Others (Operation Management)
	PWR Secondary Water Chemistry Control Using High pH with Ethanolamine	The Kansai Electric Power Co., Inc.
NT16	I: Inspection
	Wall thinning inspection technique for large-diameter piping by a partially attached-type guided wave sensor	Hitachi, Ltd. Hitachi-GE Nuclear Energy, Ltd.
NT17	I: Inspection
	Application of 3D Ultrasonic Inspection System for pipe wall thinning	TOSHIBA Corporation
NT18	II: Repair
	Actual Stress and Thickness Measurement for Steel Pipes Using Electro-magnetic Acoustic Transducer	Nichizo Tech Inc. Osaka University

Vol1. No.3 (November, 2010)
General Articles
GA6	China's Nuclear Industry at a Turning Point	Hideo KUBOTA
GA7	Efforts toward Enhancing Seismic Safety at Kashiwazaki Kariwa Nuclear Power Station	Kazuhiko YAMASHITA
Academic Articles
AA8	Contributed Paper pp.83-86
	Electromagnetic Nondestructive Evaluation of Rotating Blades	Daigo KOSAKA, et al.
AA9	Technical Note pp.87-98
	Manufacturing of Low Neutron Irradiation Embrittlement Sensitivity Core Region Shells for Nuclear Reactor Pressure Vessels Manufacturing of Low Neutron Irradiation Embrittlement Sensitivity Core Region Shells for Nuclear Reactor Pressure Vessels	Mikio KUSUHASHI, et al.
New Technology
NT10	V: Others (Operation Management)
	Hydrogen Water Chemistry During Start-Up (HDS)	The Japan Atomic Power Company (JAPC)
NT11	IV: Preventive Maintenance
	RESIDUAL STRESS IMPROVEMENT FOR NICKEL BASED ALLOY PWSCC MITIGATION BY ULTRASONIC SHOT PEENING	MITSUBISHI HEAVY INDUSTRIES, LTD.
NT12	IV: Preventive Maintenance
	Laser Peening Technology for Preventing Stress Corrosion Cracking for BWR reactor internals	TOSHIBA CORPORATION
NT13	II: Repair
	Crack Removing Method for Repair of Reactor Internals	Hitachi-GE Nuclear Energy, Ltd.

	(SheetA) Core shroud crack Removing Method by Electric Discharge Machining	Hitachi-GE Nuclear Energy, Ltd.

	(SheetB) Core shroud crack Removing Method by Grinding	Hitachi-GE Nuclear Energy, Ltd.

Vol.1 No.2 (August, 2009)
General Articles
GA5	Basic Concept and Its Aims of E-Journal of Advanced Maintenance (EJAM)	Kenzo MIYA
Academic Articles
AA6	Contributed Paper pp.68-76
	Investigations of Multi-frequency Algorithms for Detection of Defects in FBR Magnetic Steam Generators Tubes Covered with Sodium	Ovidiu MIHALACHE, et al.
AA7	Contributed Paper pp.77-82
	Non-destructive Evaluation of Fatigue Damage in the Stainless Steel by Using Electromagnetic Method	Mohachiro OKA, et al.
New Technology
NT7	IV: Preventive Maintenance
	Water Jet Peening Technology for Preventing Stress Corrosion Cracking by Using Cavitations	Hitachi-GE Nuclear Energy, Ltd. Mitsubishi Heavy Industries, Ltd.
NT7(1)	V: Others (Operation Management)
	The Water Jet Peening for Reactor Internals Technology for Preventing Stress Corrosion Cracking by Using Cavitations	Hitachi-GE Nuclear Energy, Ltd.
NT7(2)	IV: Preventive Maintenance
	WATER JET PEENING AS RESIDUAL STRESS IMPROVEMENT METHOD FOR ALLOY 600 PWSCC MITIGATION	MITSUBISHI HEAVY INDUSTRIES, LTD.
NT8	IV: Preventive Maintenance
	LDT (Laser Desensitization Treatment) Preventive Maintenance Technique for Reactor Internal Piping	TOSHIBA Corporation
NT9	IV: Preventive Maintenance
	HSW (Heat Sink Welding) Preventive Maintenance Technique for Primary Loop Recirculation Piping	Toshiba Corporation

Vol.1 No.1 (May, 2009)
General Articles
GA1	Preface The Purpose of E-journal of Advanced Maintenance	Kenzo MIYA
GA2	Structurization of Maintenology and its Systematization	Hiroshi MIYANO
GA3	Virtual Plant and Maintenance Revolution	Kenzo MIYA
GA4	Green Energy and Nuclear Energy	Masato IDESAWA
Academic Articles
AA1	Invited Paper pp.1-29
	Stress Corrosion Cracking in Low Carbon Stainless Steel Components in BWRs	Shunichi SUZUKI, et al.
AA2	Invited Paper pp.30-43
	Research priorities at the European Commission in relation to Maintenance Optimisation and Nuclear Power Plant Life Management	Paolo CONTRI
AA3	Contributed Paper pp.68-76
	Examination of Relation between IASCC Susceptibility and Magnetic Property	Shigeru TAKAYA, et al.
AA4	Contributed Paper pp.44-51
	Investigations of Multi-frequency Algorithms for Detection of Defects in FBR Magnetic Steam Generators Tubes Covered with Sodium	Ovidiu MIHALACHE, et al.
AA5	Technical Note pp.63-67
	Progress of Performance Demonstration in Japan	Toshihiko SASAHARA, et al.
New Technology
NT1	I: Inspection
	Simulation Technique for UT Wave Propagation as an Effective Tool for Predicting the Inspection Results and Interpreting the Root Cause of Unexpected Indications	Ichiro KOMURA Takashi FURUKAWA
NT2	II: Repair
	Seal Welding of PWSCC at J-Weld of Reactor Vessel Head Penetration Nozzle	The Kansai Electric Power Co., INC. Mitsubishi Heavy Industries, LTD.
NT3	II: Repair
	Seal-Welding over Cracks for Preventing SCC Propagation	Takashi Ito, Hitachi-GE Nuclear Energy, Ltd. Tooru Ootubo, Toshiba Corporation

	(Sheet A) Laser Seal-welding

	(Sheet B) Underwater TIG Seal-welding
NT4	IV: Preventive Maintenance
	CRC (Corrosion Resistant Cladding) Preventive Maintenance Technique for Primary Loop Recirculation Piping	Toshiba Corporation
NT5	IV: Preventive Maintenance
	Internal Polishing Preventive Maintenance Technique for Primary Loop Recirculation Piping	Toshiba Corporation
NT6	IV: Preventive Maintenance
	IHSI (Induction Heating Stress Improvement) Preventive Maintenance Technique for Primary Loop Recirculation Piping	Toshiba Corporation

	(Sheet A) Preventive Maintenance and Repair for PLR Piping	Toshiba Corporation，Hitachi-GE Nuclear Energy, Ltd.


	ICMST-Tohoku 2018 Oct. 23 - 26, 2018 Sendai, Japan
	ICMST-Shenzhen 2016 Nov 1 - 4, 2016 Shenzhen, China (EXIT THIS PAGE)
	ICMST-Kobe 2014 Nov 2(Sun) - 5(Wed), 2014 Kobe, Japan
Nuclear Regulation Authority	Outline of the New Safety Standards for Light Water Reactors for Electric Power Generation
	For Public Comment Outline of New Safety Standard (Design Basis)
	For Public Comment New Safety Standards (SA) Outline (Draft)
	For Public Comment Outline of New Safety Standard(Earthquake and Tsunami)(DRAFT)