E-Journal of Advanced Maintenance (EJAM)

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OTjapan Measures for Tsunami Striking Nuclear Power Station in Japan Special Article: The Great Tohoku Earthquake (1)
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Featured Articles
EJAM7-3NT72	A New Mechanical Condition-based Maintenance Technology Using Instrumented Indentation Technique
EJAM7-3NT73	Survey robots for Fukushima Daiichi Nuclear Power Plant

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

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

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

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.