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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)
Issues
 

Vol.8 No.2(Aug-25)
Vol.8 No.1(May-25)
Vol.7 No.4(Feb-25)
Vol.7 No.3(Nov-25)
Vol.7 No.2(Aug-25)
Vol.7 No.1(May-25)

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Occasional Topics
OTjapan Measures for Tsunami Striking Nuclear Power Station in Japan
Special Article: The Great Tohoku Earthquake (1)
OTjapan The Tragedy of “To Be” Principle in the Japanese Nuclear Industry
EJAMOT_CN3_Figure1_The_outside_view_of_CEFR OTChinaPlanning and Consideration on SFR R&D Activities in China
< All Occasional Topics

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

JSM
Contacts
(EJAM): ejam@jsm.or.jp
(JSM): secretariat@jsm.or.jp
HP: http://www.jsm.or.jp
(in English)

Vol.9 No.1 (May, 2017)
Academic Articles
Special Issue 16 (Guest editor: K. Demachi)
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)
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)
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)
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)
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)
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)
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)
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)
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)
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)
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
Pt Deposition Treatment Combined with Chemical Decontamination 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)
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-3TM 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)
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)
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)
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)
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)
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)
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 Koji DOZAKI 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 VesselsManufacturing 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)
PWR Secondary Water Chemistry Control Using High pH with Ethanolamine The Kansai Electric Power Co., Inc.
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.