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Proceedings Papers

Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan

Hiroki Yada, Takashi Wakai, Takayuki Miyagawa, Hideo Machida

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A060, July 13–15, 2021

Paper No: PVP2021-61942

DOI: https://doi.org/10.1115/PVP2021-61942

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Topics: Fast neutron reactors, Fracture (Materials), In-service inspection, Leakage, Leak-before-break, Sodium, Sodium fast reactors

Proceedings Papers

Example Proposals of Fracture Controlled Vessels and Piping for Failure Mitigations

Naoto Kasahara, Takashi Wakai, Izumi Nakamura, Takuya Sato, Masakazu Ichimiya

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A031, July 13–15, 2021

Paper No: PVP2021-61952

DOI: https://doi.org/10.1115/PVP2021-61952

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Topics: Design, Failure, Fracture (Materials), Fracture (Process), Pipes, Vessels

Proceedings Papers

Proposal of Simulation Material Test Technique for Clarifying the Structure Failure Mechanisms Under Excessive Seismic Loads

Ryuta Hashidate, Shoichi Kato, Takashi Onizawa, Takashi Wakai, Naoto Kasahara

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A029, July 13–15, 2021

Paper No: PVP2021-61866

DOI: https://doi.org/10.1115/PVP2021-61866

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Topics: Constitutive equations, Failure mechanisms, Lead alloys, Simulation, Stress

Proceedings Papers

Proposal of Simulation Materials Test Technique and Their Constitutive Equations for Structural Tests and Analyses Simulating Severe Accident Conditions

Ryuta Hashidate, Shoichi Kato, Takashi Onizawa, Takashi Wakai, Naoto Kasahara

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A041, August 3, 2020

Paper No: PVP2020-21397

DOI: https://doi.org/10.1115/PVP2020-21397

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Topics: Accidents, Constitutive equations, Lead alloys, Simulation

Proceedings Papers

Application of Fracture Control to Mitigate Failure Consequence Under BDBE

Naoto Kasahara, Takashi Wakai, Izumi Nakamura, Takuya Sato, Masakazu Ichimiya

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A038, August 3, 2020

Paper No: PVP2020-21072

DOI: https://doi.org/10.1115/PVP2020-21072

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Topics: Design, Failure, Failure mechanisms, Fracture (Materials), Fracture (Process)

Proceedings Papers

Research Plan and Progress to Realize Fracture Control of Nuclear Components

Naoto Kasahara, Takashi Wakai, Izumi Nakamura, Takuya Sato

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A039, July 14–19, 2019

Paper No: PVP2019-93545

DOI: https://doi.org/10.1115/PVP2019-93545

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Topics: Design, Failure mechanisms, Fracture (Materials)

Proceedings Papers

A Proposal of Inelastic Constitutive Equations of Lead Alloys Used for Structural Tests Simulating Severe Accident Conditions

Ryuta Hashidate, Takashi Onizawa, Takashi Wakai, Naoto Kasahara

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A040, July 14–19, 2019

Paper No: PVP2019-93820

DOI: https://doi.org/10.1115/PVP2019-93820

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Topics: Accidents, Constitutive equations, Lead alloys

Proceedings Papers

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Seiji Yanagihara, Ryosuke Suzuki, Masaaki Matsubara

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A035, July 22–26, 2018

Paper No: ICONE26-82619

DOI: https://doi.org/10.1115/ICONE26-82619

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Topics: Displacement, Fracture (Materials), Pipes, Steel, Thin wall structures, Leakage, Sodium fast reactors, Sodium, Work hardening, Coolants

Proceedings Papers

Proposal of Simplified J-Integral Evaluation Method for a Through Wall Crack in SFR Pipe Made of Mod.9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Koichi Kikuchi

Proc. ASME. ETAM2018, ASME 2018 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, V001T03A001, April 3–5, 2018

Paper No: ETAM2018-6708

DOI: https://doi.org/10.1115/ETAM2018-6708

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Topics: Evaluation methods, Fracture (Materials), Pipes, Sodium fast reactors, Steel, Finite element analysis, Stress, Failure analysis, Coolants, Cylinders

Proceedings Papers

Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

Tai Asayama, Yugi Nagae, Takashi Wakai, Kazuyuki Tsukimori, Masaki Morishita

Proc. ASME. ETAM2014, ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, 296-302, March 25–27, 2014

Paper No: ETAM2014-1037

DOI: https://doi.org/10.1115/ETAM2014-1037

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Topics: Sodium fast reactors, Design, Fast neutron reactors, Japan Society of Mechanical Engineers, Construction, Cycles, Fitness-for-service, Industrial research, Leak-before-break, Reliability

Proceedings Papers

The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature

Kenta Shimomura, Takashi Onizawa, Shoichi Kato, Masanori Ando, Takashi Wakai

Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A006, July 16–20, 2017

Paper No: PVP2017-65666

DOI: https://doi.org/10.1115/PVP2017-65666

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Topics: High temperature, Stainless steel, Accidents, Nuclear power stations, Creep, Numerical analysis, Safety, Finite element analysis, Finite element methods, Fukushima nuclear disaster, Japan, 2011

Proceedings Papers

Thermal Fatigue Test on Dissimilar Welded Joint Between Gr.91 and 304SS

Takashi Wakai, Sumio Kobayashi, Shoichi Kato, Masanori Ando, Hideki Takasho

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A008, July 2–6, 2017

Paper No: ICONE25-66099

DOI: https://doi.org/10.1115/ICONE25-66099

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Topics: Fatigue testing, Welded joints, Steel, Fatigue damage, Creep, Evaluation methods, Fatigue, Fatigue cracks, Finite element analysis, Alloys

Proceedings Papers

Development of Seismic Isolation Systems for Sodium-Cooled Fast Reactors in Japan

Nobuchika Kawasaki, Tomoyoshi Watakabe, Takashi Wakai, Tomohiko Yamamoto, Tsuyoshi Fukasawa, Shigeki Okamura

Proc. ASME. PVP2016, Volume 8: Seismic Engineering, V008T08A037, July 17–21, 2016

Paper No: PVP2016-63437

DOI: https://doi.org/10.1115/PVP2016-63437

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Topics: Sodium fast reactors, Springs, Dampers, Design, Disks, Bearings, Buckling, Damping, Diluents, Earthquake resistant design

Journal Articles

The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor

Takuya Yamashita, Takashi Wakai, Takashi Onizawa, Kenichiro Satoh, Kenji Yamamoto

J. Pressure Vessel Technol. December 2016, 138(6): 061403.

Paper No: PVT-15-1260

DOI: https://doi.org/10.1115/1.4034017

Published Online: September 2, 2016

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Topics: Base metals, Creep, Rupture, Sodium fast reactors, Steel, Stress, Welded joints, Temperature, Design

Journal Articles

A Screening Method for Prevention of Ratcheting Strain Derived From Movement of Temperature Distribution

Satoshi Okajima, Takashi Wakai, Masanori Ando, Yasuhiro Inoue, Sota Watanabe

J. Pressure Vessel Technol. October 2016, 138(5): 051204.

Paper No: PVT-15-1222

DOI: https://doi.org/10.1115/1.4032989

Published Online: April 29, 2016

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Topics: Membranes, Stress, Temperature, Temperature distribution, Design

Proceedings Papers

Development of Structural Codes for JSFR Based on the System Based Code Concept

Tai Asayama, Takashi Wakai, Masanori Ando, Satoshi Okajima, Yuji Nagae, Shigeru Takaya, Takashi Onizawa, Kazuyuki Tsukimori, Masaki Morishita

Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A064, July 20–24, 2014

Paper No: PVP2014-28853

DOI: https://doi.org/10.1115/PVP2014-28853

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Topics: Construction, Design, Fast neutron reactors, Fitness-for-service, Industrial research, Japan Society of Mechanical Engineers, Leak-before-break, Reliability, Sodium fast reactors, Welding

Proceedings Papers

Proposal of the Screening Method for Prevention of the Accumulation of the Ratcheting Strain Derived From the Movement of the Temperature Distribution

Satoshi Okajima, Takashi Wakai, Masanori Ando, Yasuhiro Inoue, Sota Watanabe

Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A065, July 20–24, 2014

Paper No: PVP2014-28875

DOI: https://doi.org/10.1115/PVP2014-28875

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Topics: Temperature distribution, Stress, Deformation, Design, Evaluation methods, Cylinders, Finite element methods, Wall thickness, Yield strength, Bending (Stress)

Proceedings Papers

A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)

Takashi Wakai, Takashi Onizawa, Takehiko Kato, Shingo Date, Koichi Kikuchi, Kenichiro Satoh

Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A105, July 14–18, 2013

Paper No: PVP2013-97091

DOI: https://doi.org/10.1115/PVP2013-97091

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Topics: Sodium fast reactors, Steel, Welded joints, Creep, Rupture, Stress, Base metals, Design, Temperature, Damage

Proceedings Papers

Effect of Rotational Stiffness Evolution at Crack Part on Critical Crack Size in SFR

Takashi Wakai, Hideo Machida, Shinji Yoshida

Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 713-721, July 15–19, 2012

Paper No: PVP2012-78061

DOI: https://doi.org/10.1115/PVP2012-78061

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Topics: Fracture (Materials), Sodium fast reactors, Stiffness, Pipes, Displacement, Stress, Evaluation methods, Leak-before-break, Piping systems, Springs

Journal Articles

Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Shinji Yoshida, Yasuhiro Enuma

J. Pressure Vessel Technol. February 2013, 135(1): 011401.

Paper No: PVT-11-1116

DOI: https://doi.org/10.1115/1.4007642

Published Online: December 4, 2012

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Topics: Displacement, Finite element analysis, Fracture (Materials), Pipes, Sodium fast reactors, Steel, Tension, Thin wall structures, Stress, Leak-before-break

Journal citation

NARROW

Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan

Example Proposals of Fracture Controlled Vessels and Piping for Failure Mitigations

Proposal of Simulation Material Test Technique for Clarifying the Structure Failure Mechanisms Under Excessive Seismic Loads

Proposal of Simulation Materials Test Technique and Their Constitutive Equations for Structural Tests and Analyses Simulating Severe Accident Conditions

Application of Fracture Control to Mitigate Failure Consequence Under BDBE

Research Plan and Progress to Realize Fracture Control of Nuclear Components

A Proposal of Inelastic Constitutive Equations of Lead Alloys Used for Structural Tests Simulating Severe Accident Conditions

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Proposal of Simplified J-Integral Evaluation Method for a Through Wall Crack in SFR Pipe Made of Mod.9Cr-1Mo Steel

Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature

Thermal Fatigue Test on Dissimilar Welded Joint Between Gr.91 and 304SS

Development of Seismic Isolation Systems for Sodium-Cooled Fast Reactors in Japan

The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor

A Screening Method for Prevention of Ratcheting Strain Derived From Movement of Temperature Distribution

Development of Structural Codes for JSFR Based on the System Based Code Concept

Proposal of the Screening Method for Prevention of the Accumulation of the Ratcheting Strain Derived From the Movement of the Temperature Distribution

A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)

Effect of Rotational Stiffness Evolution at Crack Part on Critical Crack Size in SFR

Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

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