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Journal Articles

Introduction to plasma fusion energy

Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.

Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03

no abstracts in English

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

JSME International Journal, Series A, 45(1), p.104 - 109, 2002/01

no abstracts in English

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.93 - 99, 2001/06

no abstracts in English

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with superior creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

Nihon Gakujutsu Shinkokai Genshiro Zairyo Dai-122-Iinkai Shiryoshu, p.279 - 282, 2000/11

no abstracts in English

JAEA Reports

Study on development of filler metal for Ni-Cr-W superalloy (Joint research)

Saito, T.*; ; Takatsu, T.*; Tsuji, Hirokazu; Shindo, Masami; Nakajima, Hajime

JAERI-Research 99-036, 99 Pages, 1999/05

JAERI-Research-99-036.pdf:29.53MB

no abstracts in English

Journal Articles

Shielding analyses of the ITER NBI ports

Sato, Satoshi; Takatsu, Hideyuki; Seki, Yasushi; *; *; Iida, Hiromasa; Plenteda, R.*; Santoro, R. T.*; Valenza, D.*; Ohara, Yoshihiro; et al.

Fusion Technology, 34(3), p.1002 - 1007, 1998/11

no abstracts in English

Journal Articles

Low cycle fatigue lifetime of HIP bonded Bi-metallic first wall structures of fusion reactors

Hatano, Toshihisa; Sato, Satoshi; Hashimoto, T.*; Kitamura, Kazunori*; Furuya, Kazuyuki; Kuroda, Toshimasa*; Enoeda, Mikio; Takatsu, Hideyuki

Journal of Nuclear Science and Technology, 35(10), p.705 - 711, 1998/10

 Times Cited Count:1 Percentile:15.43(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Creep rupture properties of trial welded joints of a Ni-Cr-W superalloy in air environment

; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

JAERI-Research 97-032, 20 Pages, 1997/05

JAERI-Research-97-032.pdf:1.78MB

no abstracts in English

Journal Articles

Design development of shieldingblanket for fusion experimental reactors

Furuya, Kazuyuki; *; Miura, H.*; *; Kurasawa, Toshimasa; Kuroda, Toshimasa*; *; Sato, Satoshi; Hatano, Toshihisa; Takatsu, Hideyuki; et al.

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.256 - 259, 1996/00

no abstracts in English

Journal Articles

Present activities preparation of a Japanese draft of structural design guidelines for the experimental fusion reactor

Miya, Kenzo*; ; Takatsu, Hideyuki; Hada, Kazuhiko; Koizumi, Koichi; Jitsukawa, Shiro; ; Okawa, Yoshinao; Shimakawa, T.*; Aoto, Kazumi*; et al.

Fusion Engineering and Design, 31, p.145 - 165, 1996/00

 Times Cited Count:3 Percentile:33.29(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Mechanical properties of HIP bonded joints of austenitic stainless steel and Cu-alloy for fusion experimental reactor blanket

Sato, Satoshi; Takatsu, Hideyuki; Hashimoto, T.*; Kurasawa, Toshimasa; Furuya, Kazuyuki; *; Osaki, Toshio*; Kuroda, Toshimasa*

Journal of Nuclear Materials, 233-237(PT.B), p.940 - 944, 1996/00

 Times Cited Count:34 Percentile:92.49(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Transient thermal and stress analyses of the ITER shielding blanket/first wall under off-normal conditions

Furuya, Kazuyuki; Hashimoto, T.*; Sato, Satoshi; Kuroda, Toshimasa*; *; Kurasawa, Toshimasa; *; Takatsu, Hideyuki

JAERI-Tech 95-045, 53 Pages, 1995/09

JAERI-Tech-95-045.pdf:3.13MB

no abstracts in English

JAEA Reports

Integration of test modules in the main blanket and vacuum vessel design

Nakahira, Masataka; Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 95-035, 20 Pages, 1995/07

JAERI-Tech-95-035.pdf:0.64MB

no abstracts in English

JAEA Reports

Convertible shielding to ceramic breeding blanket

Furuya, Kazuyuki; Kurasawa, Toshimasa; Sato, Satoshi; Nakahira, Masataka; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 95-031, 19 Pages, 1995/05

JAERI-Tech-95-031.pdf:0.72MB

no abstracts in English

JAEA Reports

Test program development for ITER blanket design

Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; Nakahira, Masataka; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 95-021, 25 Pages, 1995/03

JAERI-Tech-95-021.pdf:0.97MB

no abstracts in English

JAEA Reports

Conceptual design of ITER shielding blanket

Sato, Satoshi; Takatsu, Hideyuki; Kurasawa, Toshimasa; Hashimoto, T.*; Koizumi, Koichi; *; *; *; Tada, Eisuke; Nakahira, Masataka; et al.

JAERI-Tech 95-019, 129 Pages, 1995/03

JAERI-Tech-95-019.pdf:3.27MB

no abstracts in English

Journal Articles

Ceramic breeding blanket development for experimental fusion reactor in JAERI

Kurasawa, Toshimasa; Takatsu, Hideyuki; Sato, Satoshi; Mori, Seiji*; Hashimoto, T.*; Nakahira, Masataka; Furuya, Kazuyuki; Tsunematsu, Toshihide; Seki, Masahiro; Kawamura, Hiroshi; et al.

Fusion Engineering and Design, 27, p.449 - 456, 1995/00

 Times Cited Count:7 Percentile:60.06(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Design and R&D activities on ceramic breeder blanket for fusion experimental reactors in JAERI

Kurasawa, Toshimasa; Takatsu, Hideyuki; Sato, Satoshi; Nakahira, Masataka; Furuya, Kazuyuki; Hashimoto, T.*; Kawamura, Hiroshi; Kuroda, Toshimasa*; Tsunematsu, Toshihide; Seki, Masahiro

Fusion Technology 1994, Vol.2, 0, p.1233 - 1236, 1995/00

no abstracts in English

JAEA Reports

Peaking factors of nuclear heating due to void ducts in the 80% SS-20% H$$_{2}$$O shielding blanket of fusion experimental reactors

S.Zimin*; Sato, Satoshi; Hashimoto, T.*; Takatsu, Hideyuki

JAERI-Tech 94-026, 13 Pages, 1994/11

JAERI-Tech-94-026.pdf:0.32MB

no abstracts in English

JAEA Reports

Development and trial manufacturing of 1/2-scale partial mock-up of blanket box structure for fusion experimental reactor

Hashimoto, T.*; Takatsu, Hideyuki; Sato, Satoshi; Kurasawa, Toshimasa; Mori, Seiji*; Tada, Eisuke; Kuroda, Toshimasa*; Mori, Kensuke*; *; Seki, Masahiro

JAERI-Tech 94-009, 70 Pages, 1994/07

JAERI-Tech-94-009.pdf:5.11MB

no abstracts in English

22 (Records 1-20 displayed on this page)