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1

[ASME ASME 2013 Pressure Vessels and Piping Conference - Paris, France (Sunday 14 July 2013)] Volume 1B: Codes and Standards - Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (4) Creep–Fatigue Evaluation Method for Modified 9Cr–1Mo Steel

Takaya, Shigeru, Nagae, Yuji, Asayama, Tai

Année:

2013

Langue:

english

Fichier:

PDF, 1.96 MB

english, 2013

2

Formation of nano-size oxide particles and δ-ferrite at elevated temperature in 9Cr-ODS steel

Sawoong Kim, Satoshi Ohtsuka, Takeji Kaito, Shinichiro Yamashita, Masaki Inoue, Tai Asayama, Takahisa Shobu

Journal:

Journal of Nuclear Materials

Année:

2011

Langue:

english

Fichier:

PDF, 1.08 MB

english, 2011

3

[ASME ASME 2008 Pressure Vessels and Piping Conference - Chicago, Illinois, USA (July 27–31, 2008)] Volume 1: Codes and Standards - An Overview of Creep-Fatigue Damage Evaluation Methods and an Alternative Approach

Asayama, Tai, Jetter, Robert

Année:

2008

Langue:

english

Fichier:

PDF, 302 KB

english, 2008

4

[ASME ASME 2013 Pressure Vessels and Piping Conference - Paris, France (Sunday 14 July 2013)] Volume 1B: Codes and Standards - Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel

Onizawa, Takashi, Nagae, Yuji, Takaya, Shigeru, Asayama, Tai

Année:

2013

Langue:

english

Fichier:

PDF, 1.06 MB

english, 2013

5

[ASME ASME 2012 Pressure Vessels and Piping Conference - Toronto, Ontario, Canada (Sunday 15 July 2012)] Volume 1: Codes and Standards - Application of the System Based Code Concept to the ASME Code for Liquid Metal Reactors

Asayama, Tai, Takaya, Shigeru, Morishita, Masaki

Année:

2012

Langue:

english

Fichier:

PDF, 278 KB

english, 2012

6

[ASME ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference - Bellevue, Washington, USA (July 18–22, 2010)] ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B - Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 2—Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Wakai, Takashi, Machida, Hideo, Arakawa, Manabu, Enuma, Yasuhiro, Asayama, Tai

Année:

2010

Langue:

english

Fichier:

PDF, 724 KB

english, 2010

7

[ASME ASME 2013 Pressure Vessels and Piping Conference - Paris, France (Sunday 14 July 2013)] Volume 1B: Codes and Standards - Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (3) Development of the Material Strength Standard of Modified 9Cr-1Mo Steel

Onizawa, Takashi, Nagae, Yuji, Takaya, Shigeru, Asayama, Tai

Année:

2013

Langue:

english

Fichier:

PDF, 1.21 MB

english, 2013

8

Development of Elevated Temperature Structual Design Standard and Three-Dimensional Seismic Isolation Technology for Advanced Nuclear Power Plant; 発電用新型炉の高温構造設計手法と3次元免震技術の開発;

INOUE, Kazuhiko, SHIBAMOTO, Hiroshi, TAKAHASHI, Kenji, IKUTAMA, Shinya, MORISHITA, Masaki, AOTO, Kazumi, KASAHARA, Naoto, ASAYAMA, Tai, KITAMURA, Seiji

Journal:

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

Année:

2006

Fichier:

PDF, 4.49 MB

2006

9

Effect of nonproportional loading on creep-fatigue properties of 304 stainless steel at low strain ranges near the elastic region

Tai Asayama, Kazumi Aoto, Yuusaku Wada

Journal:

Nuclear Engineering and Design

Année:

1993

Langue:

english

Fichier:

PDF, 820 KB

english, 1993

10

Development of high-chromium steel for the sodium-cooled fast reactor in Japan and creep–fatigue assessment of the steel

Takashi Wakai, Masayuki Sukekawa, Shingo Date, Tai Asayama, Kazumi Aoto, Shigenobu Kubo

Journal:

International Journal of Pressure Vessels and Piping

Année:

2008

Langue:

english

Fichier:

PDF, 304 KB

english, 2008

11

Weld metal creep–fatigue life prediction by modeling the microstructure degradation due to the exposure to high temperature and load

Tai Asayama, Shinich Hasebe

Journal:

Nuclear Engineering and Design

Année:

2000

Langue:

english

Fichier:

PDF, 1.01 MB

english, 2000

12

Creep–fatigue evaluation of stainless steel welded joints in FBR class 1 components

Journal:

Nuclear Engineering and Design

Année:

2000

Langue:

english

Fichier:

PDF, 493 KB

english, 2000

13

Balancing material selection and inspection requirements in structural design of fast breeder reactors based on “System Based Code” concept

Tai Asayama, Nobuchika Kawasaki, Masaki Morishita, Hiroshi Shibamoto, Kazuhiko Inoue

Journal:

Nuclear Engineering and Design

Année:

2008

Langue:

english

Fichier:

PDF, 342 KB

english, 2008

14

Creep-Fatigue Evaluation Methodologies and Related Issues for Japan Sodium Cooled Fast Reactor (JSFR)

Asayama, Tai, Takaya, Shigeru, Nagae, Yuji, Ando, Masanori, Tsukimori, Kazuyuki

Journal:

Procedia Engineering

Année:

2013

Langue:

english

Fichier:

PDF, 152 KB

english, 2013

15

Development of Creep–Fatigue Evaluation Method for 316FR Stainless Steel

Nagae, Yuji, Takaya, Shigeru, Asayama, Tai

Journal:

Journal of Pressure Vessel Technology

Année:

2015

Langue:

english

Fichier:

PDF, 569 KB

english, 2015

16

[ASME ASME 2009 Pressure Vessels and Piping Conference - Prague, Czech Republic (July 26–30, 2009)] Volume 1: Codes and Standards - Methodology for the Determination of a Set of Safety Factors That are Consistent for Design Code and Fitness-for-Service Code: Case Study for Fast Breeder Reactors

Année:

2009

Langue:

english

Fichier:

PDF, 231 KB

english, 2009

17

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] 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 - Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview

Asayama, Tai, Miyagawa, Takayuki, Dozaki, Koji, Kamishima, Yoshio, Hayashi, Masaaki, Machida, Hideo

Année:

2014

Langue:

english

Fichier:

PDF, 1.16 MB

english, 2014

18

Study on Minimum Wall Thickness Requirement for Seismic Buckling of Reactor Vessel Based on System Based Code Concept

Takaya, Shigeru, Watanabe, Daigo, Yokoi, Shinobu, Kamishima, Yoshio, Kurisaka, Kenichi, Asayama, Tai

Journal:

Journal of Pressure Vessel Technology

Année:

2015

Langue:

english

Fichier:

PDF, 1.11 MB

english, 2015

19

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] 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 - Elaboration of the System Based Code Concept — Activities in JSME and ASME: (2) Development of Evaluation Tools Based on LRFD

Machida, Hideo, Asayama, Tai, Watanabe, Daigo, Hojo, Kiminobu, Hayashi, Masaaki

Année:

2014

Langue:

english

Fichier:

PDF, 869 KB

english, 2014

20

[ASME ASME 2009 Pressure Vessels and Piping Conference - Prague, Czech Republic (July 26–30, 2009)] Volume 1: Codes and Standards - Development of a Material Strength Standard for Japanese Demonstration Fast Breeder Reactor

Onizawa, Takashi, Nagae, Yuji, Wakai, Takashi, Asayama, Tai

Année:

2009

Langue:

english

Fichier:

PDF, 240 KB

english, 2009

21

[ASME ASME 2013 Pressure Vessels and Piping Conference - Paris, France (Sunday 14 July 2013)] Volume 1B: Codes and Standards - Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (5) Creep-Fatigue Evaluation Method for 316FR Stainless Steel

Nagae, Yuji, Takaya, Shigeru, Asayama, Tai

Année:

2013

Langue:

english

Fichier:

PDF, 876 KB

english, 2013

22

Determination of in-service inspection requirements for fast reactor components using System Based Code concept

Takaya, Shigeru, Kamishima, Yoshio, Machida, Hideo, Watanabe, Daigo, Asayama, Tai

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 1.71 MB

english, 2016

23

Analysis of Thermal Fatigue Crack Propagation Based on Local Approach to Fracture

TAKAGAKI, Masakazu, TOI, Yutaka, ASAYAMA, Tai

Journal:

Journal of Solid Mechanics and Materials Engineering

Année:

2008

Langue:

english

Fichier:

PDF, 415 KB

english, 2008

24

Creep-Fatigue Evaluation by Hysteresis Energy in Modified 9Cr-1Mo Steel

NAGAE, Yuji, TAKAYA, Shigeru, ASAYAMA, Tai

Journal:

Journal of Solid Mechanics and Materials Engineering

Année:

2009

Langue:

english

Fichier:

PDF, 336 KB

english, 2009

25

Development of System Based Code (1) Reliability Target Derivation of Structures and Components

KURISAKA, Kenichi, NAKAI, Ryodai, ASAYAMA, Tai, TAKAYA, Shigeru

Journal:

Journal of Power and Energy Systems

Année:

2011

Langue:

english

Fichier:

PDF, 404 KB

english, 2011

26

10.1299/kikaia.53.2232

ASAYAMA, Tai, CHENG, Shi-Zhen, TACHIBANA, Yukio, ASADA, Yasuhide

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A

Année:

1987

Fichier:

PDF, 962 KB

1987

27

10.1299/kikaia.55.1264

ASAYAMA, Tai, TACHIBANA, Yukio, ASADA, Yasuhide

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A

Année:

1989

Fichier:

PDF, 648 KB

1989

28

Estimation of Crack Propagation by The Analysis of Thermal Fatigue Based on Local Approach Fracture

TAKAGAKI, Masakazu, TOI, Yutaka, ASAYAMA, Tai

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A

Année:

2006

Fichier:

PDF, 915 KB

2006

29

Development of the JSME Rules on Design and Construction for Nuclear Power Plants (Division 2: Fast Reactors)

ASAYAMA, Tai, NAKAYAMA, Yasunari

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A

Année:

2012

Fichier:

PDF, 684 KB

2012

30

Development of System Based Code (2) Application of Reliability Target for Configuration of ISI Requirement

TAKAYA, Shigeru, OKAJIMA, Satoshi, KURISAKA, Kenichi, ASAYAMA, Tai, MACHIDA, Hideo, KAMISHIMA, Yoshio

Journal:

Journal of Power and Energy Systems

Année:

2011

Langue:

english

Fichier:

PDF, 320 KB

english, 2011

31

10.1299/kikaia.54.38

ASAYAMA, Tai, CHENG, Shi-Zhen, TACHIBANA, Yukio, ASADA, Yasuhide

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A

Année:

1988

Fichier:

PDF, 745 KB

1988

32

Fatigue and creep-fatigue strength of 304 steel under biaxial strain conditions.

ASAYAMA, Tai, AOTO, Kazumi, WADA, Yusaku

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A

Année:

1990

Fichier:

PDF, 550 KB

1990

33

Effect of Nano-Size Oxide Particle Dispersion and δ-Ferrite Proportion on Creep Strength of 9Cr-ODS Steel

Ohtsuka, Satoshi, Kaito, Takeji, Kim, Sawoong, Inoue, Masaki, Asayama, Tai, Ohnuma, Masato, Suzuki, Junichi

Journal:

MATERIALS TRANSACTIONS

Année:

2009

Langue:

english

Fichier:

PDF, 925 KB

english, 2009

34

Development of Creep-Fatigue Evaluation Method for Modified 9Cr-1Mo Steel

Takaya, Shigeru, Nagae, Yuji, Asayama, Tai

Journal:

Journal of Pressure Vessel Technology

Année:

2014

Langue:

english

Fichier:

PDF, 1.19 MB

english, 2014

35

[ASME ASME 2014 Pressure Vessels and Piping Conference - Anaheim, California, USA (Sunday 20 July 2014)] Volume 1: Codes and Standards - Development of Structural Codes for JSFR Based on the System Based Code Concept

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

Année:

2014

Langue:

english

Fichier:

PDF, 1.01 MB

english, 2014

36

[ASME 2016 24th International Conference on Nuclear Engineering - Charlotte, North Carolina, USA (Sunday 26 June 2016)] 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 - Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD

Takaya, Shigeru, Sasaki, Naoto, Asayama, Tai, Kamishima, Yoshio

Année:

2016

Langue:

english

Fichier:

PDF, 2.09 MB

english, 2016

37

[ASME 2016 24th International Conference on Nuclear Engineering - Charlotte, North Carolina, USA (Sunday 26 June 2016)] 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 - Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward

Asayama, Tai, Takaya, Shigeru

Année:

2016

Langue:

english

Fichier:

PDF, 1.76 MB

english, 2016

38

[ASME ASME 2013 Pressure Vessels and Piping Conference - Paris, France (Sunday 14 July 2013)] Volume 1B: Codes and Standards - Study on Minimum Wall Thickness Requirement of Reactor Vessel of Fast Reactor for Seismic Buckling by System Based Code

Takaya, Shigeru, Watanabe, Daigo, Yokoi, Shinobu, Kamishima, Yoshio, Kurisaka, Kenichi, Asayama, Tai

Année:

2013

Langue:

english

Fichier:

PDF, 892 KB

english, 2013

39

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

Asayama, Tai, Abe, Yasuhiro, Miyaji, Noriko, Koi, Mamoru, Furukawa, Tomohiro, Yoshida, Eiichi

Journal:

Journal of Pressure Vessel Technology

Année:

2001

Langue:

english

Fichier:

PDF, 753 KB

english, 2001

40

[ASME ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference - Bellevue, Washington, USA (July 18–22, 2010)] ASME 2010 Pressure Vessels and Piping Conference: Volume 3 - Creep Strength Evaluation of Welded Joint Made of Modified 9Cr-1Mo Steel for Japanese Sodium Cooled Fast Reactor (JSFR)

Wakai, Takashi, Nagae, Yuji, Onizawa, Takashi, Obara, Satoshi, Xu, Yang, Ohtani, Tomomi, Date, Shingo, Asayama, Tai

Année:

2010

Langue:

english

Fichier:

PDF, 357 KB

english, 2010

41

[ASME ASME 2009 Pressure Vessels and Piping Conference - Prague, Czech Republic (July 26–30, 2009)] Volume 1: Codes and Standards - Methodology for the Determination of a Set of Safety Factors That are Consistent for Design Code and Fitness-for-Service Code: Framework

Année:

2009

Langue:

english

Fichier:

PDF, 130 KB

english, 2009

42

Probabilistic Prediction of Crack Depth Distributions Observed in Structures Subjected to Thermal Fatigue

Asayama, Tai, Takasho, Hideki, Kato, Takehiko

Journal:

Journal of Pressure Vessel Technology

Année:

2009

Langue:

english

Fichier:

PDF, 1.22 MB

english, 2009

43

[ASME ASME 2013 Pressure Vessels and Piping Conference - Paris, France (Sunday 14 July 2013)] Volume 6A: Materials and Fabrication - Extrapolation of Creep Strength by Fracture Energy for 316FR Stainless Steel at 823K

Nagae, Yuji, Asayama, Tai

Année:

2013

Langue:

english

Fichier:

PDF, 725 KB

english, 2013

44

[ASME ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference - Bellevue, Washington, USA (July 18–22, 2010)] ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B - Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 3—Fracture Assessment Methods Considering Compliance at a Crack Part

Wakai, Takashi, Machida, Hideo, Yoshida, Shinji, Enuma, Yasuhiro, Asayama, Tai

Année:

2010

Langue:

english

Fichier:

PDF, 1.03 MB

english, 2010

45

[ASME ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference - Bellevue, Washington, USA (July 18–22, 2010)] ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B - Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 1—Study on the Premise for the Standardization of Assessment Procedure

Wakai, Takashi, Machida, Hideo, Enuma, Yasuhiro, Asayama, Tai

Année:

2010

Langue:

english

Fichier:

PDF, 832 KB

english, 2010

46

Influence of Heat Treatment on Long Term Creep Properties of 9Cr–W–Mo–V–Nb Steel

Obara, Satoshi, Wakai, Takashi, Asayama, Tai, Yamada, Yoshiyuki, Nakazawa, Takanori, Yamazaki, Masayoshi, Hongo, Hiromichi

Journal:

Tetsu-to-Hagane

Année:

2010

Fichier:

PDF, 2.36 MB

2010

47

Creep-Fatigue Interaction of 21/4Cr-1Mo Steel in a Very High Vacuum Environment

ASAYAMA, Tai, CHENG, Shi-Zhen, TACHIBANA, Yukio, ASADA, Yasuhide

Journal:

JSME international journal. Ser. A, Mechanics and material engineering

Année:

1988

Fichier:

PDF, 1.13 MB

1988

48

Development of simple estimation method for the influence of parameter uncertainty of probability distributions against evaluation result of probabilistic fracture mechanics

OKAJIMA, Satoshi, TAKAYA, Shigeru, ASAYAMA, Tai

Journal:

Transactions of the JSME (in Japanese)

Année:

2017

Langue:

english

Fichier:

PDF, 969 KB

english, 2017

49

Load and resistance factor design approach for seismic buckling of fast reactor vessels

TAKAYA, Shigeru, SASAKI, Naoto, ASAYAMA, Tai, KAMISHIMA, Yoshio

Journal:

Mechanical Engineering Journal

Année:

2017

Langue:

english

Fichier:

PDF, 492 KB

english, 2017

50

[ASME ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries - Seattle, Washington, USA (Tuesday 25 March 2014)] ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries - Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

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

Année:

2014

Langue:

english

Fichier:

PDF, 1.57 MB

english, 2014