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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

Year:

2013

Language:

english

File:

PDF, 1.96 MB

english, 2013

2

[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

Year:

2008

Language:

english

File:

PDF, 302 KB

english, 2008

3

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

Year:

2006

File:

PDF, 915 KB

2006

4

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

Year:

2012

File:

PDF, 684 KB

2012

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

Year:

2012

Language:

english

File:

PDF, 278 KB

english, 2012

6

[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

Year:

2013

Language:

english

File:

PDF, 1.06 MB

english, 2013

7

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

Takaya, Shigeru, Nagae, Yuji, Asayama, Tai

Journal:

Journal of Pressure Vessel Technology

Year:

2014

Language:

english

File:

PDF, 1.19 MB

english, 2014

8

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

Year:

2008

Language:

english

File:

PDF, 304 KB

english, 2008

9

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

Year:

2011

Language:

english

File:

PDF, 1.08 MB

english, 2011

10

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

Year:

2006

File:

PDF, 4.49 MB

2006

11

[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

Year:

2010

Language:

english

File:

PDF, 724 KB

english, 2010

12

[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

Year:

2013

Language:

english

File:

PDF, 1.21 MB

english, 2013

13

[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

Year:

2013

Language:

english

File:

PDF, 876 KB

english, 2013

14

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

Year:

2011

Language:

english

File:

PDF, 404 KB

english, 2011

15

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

Nagae, Yuji, Takaya, Shigeru, Asayama, Tai

Journal:

Journal of Pressure Vessel Technology

Year:

2015

Language:

english

File:

PDF, 569 KB

english, 2015

16

[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

Year:

2014

Language:

english

File:

PDF, 1.01 MB

english, 2014

17

DESHIMA on ASTE: On-Sky Responsivity Calibration of the Integrated Superconducting Spectrometer

Takekoshi, Tatsuya, Karatsu, Kenichi, Suzuki, Junya, Tamura, Yoichi, Oshima, Tai, Taniguchi, Akio, Asayama, Shinâichiro, Bakx, Tom J. L. C., Baselmans, Jochem J. A., Bosma, Sjoerd, Bueno, Juan, Chin

Journal:

Journal of Low Temperature Physics

Year:

2020

File:

PDF, 1.92 MB

2020

18

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

Year:

2010

File:

PDF, 2.36 MB

2010

19

[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

Year:

2009

Language:

english

File:

PDF, 240 KB

english, 2009

20

[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

Year:

2014

Language:

english

File:

PDF, 869 KB

english, 2014

21

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

Year:

2001

Language:

english

File:

PDF, 753 KB

english, 2001

22

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)

Year:

2017

Language:

english

File:

PDF, 969 KB

english, 2017

23

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

Year:

1990

File:

PDF, 550 KB

1990

24

[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

Year:

2010

Language:

english

File:

PDF, 832 KB

english, 2010

25

[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

Year:

2013

Language:

english

File:

PDF, 892 KB

english, 2013

26

[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

Year:

2009

Language:

english

File:

PDF, 130 KB

english, 2009

27

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

Year:

2009

Language:

english

File:

PDF, 1.22 MB

english, 2009

28

[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

Year:

2014

Language:

english

File:

PDF, 1.16 MB

english, 2014

29

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

Year:

1988

File:

PDF, 745 KB

1988

30

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

Year:

2017

Language:

english

File:

PDF, 492 KB

english, 2017

31

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

Year:

2009

Language:

english

File:

PDF, 925 KB

english, 2009

32

[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

Year:

2013

Language:

english

File:

PDF, 725 KB

english, 2013

33

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

Year:

2008

Language:

english

File:

PDF, 342 KB

english, 2008

34

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

Year:

2013

Language:

english

File:

PDF, 152 KB

english, 2013

35

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

Year:

2011

Language:

english

File:

PDF, 320 KB

english, 2011

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

Year:

2016

Language:

english

File:

PDF, 2.09 MB

english, 2016

37

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

Year:

1988

File:

PDF, 1.13 MB

1988

38

First light demonstration of the integrated superconducting spectrometer

Endo, Akira, Karatsu, Kenichi, Tamura, Yoichi, Oshima, Tai, Taniguchi, Akio, Takekoshi, Tatsuya, Asayama, Shin’ichiro, Bakx, Tom J. L. C., Bosma, Sjoerd, Bueno, Juan, Chin, Kah Wuy, Fujii, Yasunori, F

Journal:

Nature Astronomy

Year:

2019

Language:

english

File:

PDF, 4.40 MB

english, 2019

39

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

Year:

2009

Language:

english

File:

PDF, 336 KB

english, 2009

40

First light demonstration of the integrated superconducting spectrometer

Endo, Akira, Karatsu, Kenichi, Tamura, Yoichi, Oshima, Tai, Taniguchi, Akio, Takekoshi, Tatsuya, Asayama, Shin’ichiro, Bakx, Tom J. L. C., Bosma, Sjoerd, Bueno, Juan, Chin, Kah Wuy, Fujii, Yasunori, F

Journal:

Nature Astronomy

Year:

2019

File:

PDF, 4.40 MB

2019

41

[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: (1) Overview

Asayama, Tai, Dozaki, Koji, Otani, Tomomi, Inatomi, Takanari, Ando, Masanori

Year:

2013

Language:

english

File:

PDF, 733 KB

english, 2013

42

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

Year:

2000

Language:

english

File:

PDF, 1.01 MB

english, 2000

43

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

Journal:

Nuclear Engineering and Design

Year:

2000

Language:

english

File:

PDF, 493 KB

english, 2000

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 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

Year:

2010

Language:

english

File:

PDF, 357 KB

english, 2010

45

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

Takaya, Shigeru, Asayama, Tai, Kamishima, Yoshio, Machida, Hideo, Watanabe, Daigo, Nakai, Satoru, Morishita, Masaki

Journal:

Journal of Nuclear Engineering and Radiation Science

Year:

2015

Language:

english

File:

PDF, 5.21 MB

english, 2015

46

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

Year:

1993

Language:

english

File:

PDF, 820 KB

english, 1993

47

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

Year:

2016

Language:

english

File:

PDF, 1.71 MB

english, 2016

48

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

Year:

1987

File:

PDF, 962 KB

1987

49

10.1299/kikaia.55.1264

ASAYAMA, Tai, TACHIBANA, Yukio, ASADA, Yasuhide

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A

Year:

1989

File:

PDF, 648 KB

1989

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

Year:

2014

Language:

english

File:

PDF, 1.57 MB

english, 2014

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