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JAEA Reports

Development of HIP bonding procedure and mechanical properties of HIP bonded joints for reduced activation ferritic steel F-82H

*; Kurasawa, Toshimasa; Kuroda, Toshimasa*; Hatano, Toshihisa; Takatsu, Hideyuki

JAERI-Tech 97-013, 141 Pages, 1997/03

JAERI-Tech-97-013.pdf:16.98MB

no abstracts in English

Journal Articles

Fabrication of small-scaled shielding blanket module and first wall panel for international thermonuclear experimental reactor

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

Fusion Technology 1996, 0, p.1343 - 1346, 1997/00

no abstracts in English

Journal Articles

Design development of breeding blanket based on pebble bed concept for fusion experimental reactor

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

Fusion Technology 1996, 0, p.1339 - 1342, 1997/00

no abstracts in English

JAEA Reports

Investigation on welding and cutting methods for blanket support legs of fusion experimental reactors

*; Nakahira, Masataka; Kuroda, Toshimasa*; Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; Hatano, Toshihisa; Takatsu, Hideyuki

JAERI-Tech 96-032, 102 Pages, 1996/07

JAERI-Tech-96-032.pdf:2.72MB

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

Fabrication of HIPped first wall panel for fusion experimental reactor and preliminary analyses for its thermo-mechanical test

Sato, Satoshi; Furuya, Kazuyuki; Kuroda, Toshimasa*; Kurasawa, Toshimasa; *; Hatano, Toshihisa; Takatsu, Hideyuki; Osaki, Toshio*

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.202 - 205, 1996/00

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

https://doi.org/10.1016/S0022-3115(96)00259-0
 Times Cited Count：34 Percentile：92.12(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

JAEA Reports

Compatibility test of blanket structural materials with beryllium sphere in helium gas environment

Kurasawa, Toshimasa; Takatsu, Hideyuki; Seki, Masahiro; *; *

JAERI-Tech 95-011, 24 Pages, 1995/03

JAERI-Tech-95-011.pdf:2.09MB

no abstracts in English

Journal Articles

In situ tritium recovery from Li$$_{2}$$O irradiated in a fast neutron flux; BEATRIX-II, Phase II temperature-change canister

Slagle, O. D.*; Kurasawa, Toshimasa; Takahashi, Tadashi; Hollenberg, G. W.*; Verrall, R. A.*

Journal of Nuclear Materials, 219, p.265 - 273, 1995/03

https://doi.org/10.1016/0022-3115(94)00401-3
 Times Cited Count：4 Percentile：43.32(Materials Science, Multidisciplinary)

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

https://doi.org/10.1016/0920-3796(94)00319-3
 Times Cited Count：7 Percentile：59.53(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

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

Journal Articles

Fabrication of a blanket box structure integrated with the first wall for a fusion experimental reactor

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

15th IEEE/NPSS Symp. on Fusion Engineering,Vol. 1, 0, p.259 - 262, 1994/00

no abstracts in English

Journal Articles

The VOM/JRR-2 experiments; Performance of in-situ tritium release from the lithium ceramics

Kurasawa, Toshimasa

Journal of Nuclear Materials, 212-215, p.937 - 941, 1994/00

https://doi.org/10.1016/0022-3115(94)90973-3
 Times Cited Count：2 Percentile：28.17(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Layered pebble bed concept for ITER breeding blanket

Takatsu, Hideyuki; Mori, Seiji*; Yoshida, Hiroshi; Hashimoto, T.*; Kurasawa, Toshimasa; Koizumi, Koichi; Enoeda, Mikio; Sato, Satoshi; Kuroda, Toshimasa*; *; et al.

Fusion Technology 1992, p.1504 - 1508, 1993/00

no abstracts in English

28 (Records 1-20 displayed on this page)