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Search Results: Records 1-20 displayed on this page of 49

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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

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：91.73(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

https://doi.org/10.1016/0920-3796(94)00319-3
 Times Cited Count：7 Percentile：58.73(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

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

JAEA Reports

Japanese contributions to IAEA INTOR Workshop, phase two A, part 3, chapter VIII; Blanket and first wall

; Iida, Hiromasa; ; Adachi, Junichi*; ; Ebisawa, Katsuyuki*; ; Fukaya, Kiyoshi; ; ; et al.

JAERI-M 87-219, 336 Pages, 1988/01

JAERI-M-87-219.pdf:8.39MB

no abstracts in English

Journal Articles

In-pile tritium release behavior from lithium aluminate and lithium orthosilicate of the VOM-23 experiment

Kurasawa, T.; ; Roth, E.*; D.Volloth*

Journal of Nuclear Materials, 155-157, p.544 - 548, 1988/00

https://doi.org/10.1016/0022-3115(88)90307-8
 Times Cited Count：39 Percentile：94.02(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

In-Pile Test of Tritium Release From Tritium Breading Materials : In-situ Tritium Release Measorment from Lithium Oxide(VOM-21H Experiment)

Kurasawa, T.; ; ;

JAERI-M 86-152, 81 Pages, 1986/10

JAERI-M-86-152.pdf:1.55MB

no abstracts in English

JAEA Reports

In-Pile Experiment for Tritium Recovery from Li$$_{2}$$O(VOM-21H); Tritium Chemical Form as a Function of Sweep Gas Composition

; ; Kurasawa, T.; ;

JAERI-M 86-130, 20 Pages, 1986/09

JAERI-M-86-130.pdf:0.81MB

no abstracts in English

JAEA Reports

In-situ Tritium Release Experiment from Tritium Breeder Materials ; Meascerment Apparatus and Softy Assessment of VOM-21H and 22H,

Kurasawa, T.; ; ; ; ; ; ;

JAERI-M 86-129, 26 Pages, 1986/09

JAERI-M-86-129.pdf:0.77MB

no abstracts in English

JAEA Reports

Conpatibility of Heat Resistant Alloys Boron Carbide(5) ; Preliminary Evaluation Tests for Compatibility under Irradiation and Capsule Design(83M-8J,84M-38J,39J)

; ; ; Kurasawa, T.;

JAERI-M 86-117, 78 Pages, 1986/08

JAERI-M-86-117.pdf:3.42MB

no abstracts in English

Journal Articles

The time dependence of in-situ tritium release from lithium oxide and lithium aluminate(VOM-22H experiment)

Kurasawa, T.; ; Hollenberg, G. W.*; ; ; ; Naruse, Yuji; ; ; Konishi, Satoshi

Journal of Nuclear Materials, 141-143, p.265 - 270, 1986/00

https://doi.org/10.1016/S0022-3115(86)80048-4
 Times Cited Count：34 Percentile：93.48(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

In-situ tritium recovery experiment from lithium oxide under hign neutron fluence

Kurasawa, T.; ; ; ; ; ; ; Naruse, Yuji

Journal of Nuclear Materials, 133-134, p.196 - 200, 1985/00

https://doi.org/10.1016/0022-3115(85)90133-3
 Times Cited Count：15 Percentile：84.10(Materials Science, Multidisciplinary)

no abstracts in English

49 (Records 1-20 displayed on this page)