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Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A014, July 22–26, 2018
Paper No: ICONE26-81143
DOI: https://doi.org/10.1115/ICONE26-81143
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Topics: Cavity flows, Evaluation methods, Pipes, Thermal stratification, Flow (Dynamics), Water, Fatigue, High temperature, Temperature, Temperature profiles
Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Modeling of Evaluation Method

Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A015, July 22–26, 2018
Paper No: ICONE26-81144
DOI: https://doi.org/10.1115/ICONE26-81144
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Topics: Cavity flows, Evaluation methods, Modeling, Pipes, Thermal stratification, Fatigue, High temperature, Temperature, Water, Cycles
Proceedings Papers

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to Primary Water Stress Corrosion Cracking

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A014, July 2–6, 2017
Paper No: ICONE25-66145
DOI: https://doi.org/10.1115/ICONE25-66145
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Topics: Fracture mechanics, Stress corrosion cracking, Water, Failure, Pipes, Probability, Fracture (Materials), Pressurized water reactors, Alloys, Boiling water reactors
Proceedings Papers

Status of the JSME Codification Activities on Tornado-Generated Missile Protection for Structures of Nuclear Power Plants

Koji Shirai, Masuhiro Beppu, Hideo Hirai, Kazuhiko Yamada, Shinichi Yoshida, Yohei Shinohara
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T07A008, July 2–6, 2017
Paper No: ICONE25-67776
DOI: https://doi.org/10.1115/ICONE25-67776
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Topics: Japan Society of Mechanical Engineers, Missiles, Nuclear power stations, Design, Stress, Dynamics (Mechanics), Earthquakes, Steel, Acceptance criteria, Computers
Proceedings Papers

Proposal for Evaluation With Strain-Based Criterion of Impact Phenomena Between Steel Structure and Tornado Missile

Yuko Sakamoto, Koji Shirai, Toshiko Udagawa, Shunsuke Kondo
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A009, June 26–30, 2016
Paper No: ICONE24-60171
DOI: https://doi.org/10.1115/ICONE24-60171
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Topics: Missiles, Steel, Japan Society of Mechanical Engineers, Pressurized water reactors, Accidents, Carbon steel, Containment, Deformation, Fracture (Materials), Fracture (Process)
Proceedings Papers

Comparison of the ASME, RCC-M and ISO Requirements for Welding Qualifications and Welding Quality

Marcello Consonni, Andrew Wasylyk, Stéphane Leclerc, Walter Sperko, Philippe Malouines
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A003, June 26–30, 2016
Paper No: ICONE24-60282
DOI: https://doi.org/10.1115/ICONE24-60282
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Topics: Welding, Engineering standards, ASME Boiler and Pressure Vessel Code, Boilers, Japan Society of Mechanical Engineers, Nuclear power stations, Pressure, Pressure vessels, Welding operators
Proceedings Papers

Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward

Tai Asayama, Shigeru Takaya
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A007, June 26–30, 2016
Paper No: ICONE24-60936
DOI: https://doi.org/10.1115/ICONE24-60936
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Topics: Fast neutron reactors, Japan Society of Mechanical Engineers, Reliability, Design, In-service inspection, Buckling, Design methodology, Engineering standards, Inspection, Stress
Proceedings Papers

Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD

Shigeru Takaya, Naoto Sasaki, Tai Asayama, Yoshio Kamishima
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A010, June 26–30, 2016
Paper No: ICONE24-60964
DOI: https://doi.org/10.1115/ICONE24-60964
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Topics: Buckling, Fast neutron reactors, Japan Society of Mechanical Engineers, Reliability, Design, Stress, Probability, Vessels, Civil engineering, Earthquake risk
Proceedings Papers

Investigation of MHD RANS Modeling Base on DNS Database Under the Advanced Blanket Design Conditions Utilized Molten Salt

Naoki Osawa, Yoshinobu Yamamoto, Tomoaki Kunugi
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A049, July 7–11, 2014
Paper No: ICONE22-30712
DOI: https://doi.org/10.1115/ICONE22-30712
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Topics: Databases, Design, Magnetohydrodynamics, Modeling, Reynolds-averaged Navier–Stokes equations, Turbulence, Channel flow, Computer simulation, Fluid dynamics, Fluids
Proceedings Papers

Investigation of MHD RANS Modeling Base on DNS Database Under the Advanced Blanket Design Conditions Utilized Molten Salt

Naoki Osawa, Yoshinobu Yamamoto, Tomoaki Kunugi
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T14A005, July 7–11, 2014
Paper No: ICONE22-30653
DOI: https://doi.org/10.1115/ICONE22-30653
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Topics: Databases, Design, Magnetohydrodynamics, Modeling, Reynolds-averaged Navier–Stokes equations, Turbulence, Channel flow, Computer simulation, Fluid dynamics, Fluids
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR

Shigeru Takaya, Hideo Machida, Yoshio Kamishima
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A005, July 7–11, 2014
Paper No: ICONE22-30570
DOI: https://doi.org/10.1115/ICONE22-30570
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Topics: Japan Society of Mechanical Engineers, Reliability, Failure, Breeder reactors, Crack propagation, Creep, Damage, Fatigue, Modeling, Probability
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME

Tai Asayama, Shigeru Takaya, Masaki Morishita, Frank Schaaf
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A006, July 7–11, 2014
Paper No: ICONE22-30572
DOI: https://doi.org/10.1115/ICONE22-30572
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Topics: Japan Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Flow (Dynamics), In-service inspection, Liquid metals, Mechanical engineers, Safety, Sodium fast reactors
Proceedings Papers

Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel

Toshiari Saegusa, Makoto Hirose, Norikazu Irie, Masashi Shimizu
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A009, July 7–11, 2014
Paper No: ICONE22-30696
DOI: https://doi.org/10.1115/ICONE22-30696
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Topics: Engineering standards, Metals, Spent nuclear fuels, Storage, Stress, Containment vessels, Japan Society of Mechanical Engineers, Safety, Design, Nuclear power stations
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (2) Development of Evaluation Tools Based on LRFD

Hideo Machida, Tai Asayama, Daigo Watanabe, Kiminobu Hojo, Masaaki Hayashi
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A002, July 7–11, 2014
Paper No: ICONE22-30525
DOI: https://doi.org/10.1115/ICONE22-30525
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Topics: Japan Society of Mechanical Engineers, Reliability, Collapse, Design, Bending (Stress), Buckling, Cylinders, Failure, Failure mechanisms, Fatigue
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview

Tai Asayama, Takayuki Miyagawa, Koji Dozaki, Yoshio Kamishima, Masaaki Hayashi, Hideo Machida
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A004, July 7–11, 2014
Paper No: ICONE22-30567
DOI: https://doi.org/10.1115/ICONE22-30567
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Topics: Japan Society of Mechanical Engineers, Reliability, ASME Boiler and Pressure Vessel Code, Collaboration, Design, Engineering standards, In-service inspection, Liquid metals, Mechanical engineers, Sodium fast reactors
Proceedings Papers

Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment

Takuya Ogawa, Masao Itatani, Toshiyuki Saito, Hiroshi Nagase, Satoru Aoike, Hideki Yoneda
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A017, July 7–11, 2014
Paper No: ICONE22-31143
DOI: https://doi.org/10.1115/ICONE22-31143
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Topics: Alloys, Boiling water reactors, Fatigue cracks, Water, Stress, Fitness-for-service, Corrosion, Fracture (Materials), Japan Society of Mechanical Engineers, ASTM International
Proceedings Papers

State of the Art Study for the Basis of Pipe Wall Thinning Management in Japan

Fumio Inada, Yutaka Watanabe, Taku Ohira, Akira Nakamura
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A012, July 29–August 2, 2013
Paper No: ICONE21-15184
DOI: https://doi.org/10.1115/ICONE21-15184
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Topics: Pipes, Japan Society of Mechanical Engineers, Corrosion, Drops, Energy generation, Erosion, Flow (Dynamics), Inspection, Roads
Proceedings Papers

Applicability Study of Computed Radiography to NDE for Piping and Component in Nuclear Power Plant

Takashi Hasebe, Nobuki Tamai, Syohei Tatsuno, Yuma Itahashi, Kiyoaki Tokunou
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 87-91, May 17–21, 2010
Paper No: ICONE18-29215
DOI: https://doi.org/10.1115/ICONE18-29215
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Topics: Nondestructive evaluation, Nuclear power stations, Pipes, X-rays, Imaging, Noise (Sound), Testing, Biomedicine, Filters, Inspection
Proceedings Papers

A Technical Overview of The Japan’s Standards for Risk-Informed Decision Making

Yoshiyuki Narumiya, Mitsumasa Hirano, Masashi Hirano
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 653-659, May 17–21, 2010
Paper No: ICONE18-29946
DOI: https://doi.org/10.1115/ICONE18-29946
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Topics: Risk-based decision making, Safety, Risk, Defense industry, Nuclear power stations, Accident management, Accidents, Concretes, Fire risk, Floods
Proceedings Papers

The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators

John M. Dyke
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 393-395, April 25–29, 2004
Paper No: ICONE12-49059
DOI: https://doi.org/10.1115/ICONE12-49059
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Topics: Boilers, Coolants, Nuclear reactor steam generators, Vibration, Boiling, Bubbles, Design, Flow (Dynamics), Geometry, Japan Society of Mechanical Engineers