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Journal Articles

Discussion on translational research of drug product for targeted alpha therapy, 2

Yano, Tsuneo*; Hasegawa, Koki*; Sato, Tatsuhiko; Hachisuka, Akiko*; Fukase, Koichi*; Hirabayashi, Yoko*

Iyakuhin Iryo Kiki Regyuratori Saiensu, 50(3), p.122 - 134, 2019/03

https://www.pmrj.jp/publications/pub01_06.html

This report provides an overview of alpha-particle-emitting radiopharmaceuticals applied by micro-dosimetry.

Journal Articles

Irradiation effects of polyethylene produced by single-site catalyst

*; *; *; Yagi, Toshiaki; Morita, Yosuke

Denki Gakkai; Yuden, Zetsuen Zairyo Kenkyukai Shiryo DEI-97-147$$sim$$155, p.13 - 18, 1997/12

no abstracts in English

Journal Articles

Radiation aging and degradation mechanism of polymer insulation for electric cables

*; *; *; Seguchi, Tadao; Yagi, Toshiaki

Proc. of 46th Int. Wire and Cable Symp., p.1 - 5, 1997/00

no abstracts in English

Journal Articles

Evaluation of irradiation embrittlement of 21/4Cr-1Mo steel in terms of elastic-plastic fracture toughness

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Kodaira, Tsuneo; Oku, Tatsuo*

Effects of Radiation on Materials; 15th International Symposium (ASTM STP 1125), p.1287 - 1303, 1992/00

no abstracts in English

Journal Articles

Evaluation of toughness degradation by small punch (SP) tests for neutron-irradiated 21/4Cr-1Mo steel

Suzuki, Masahide; Eto, Motokuni; Fukaya, Kiyoshi; Nishiyama, Yutaka; Kodaira, Tsuneo; Oku, Tatsuo; ; ; ; *; et al.

Journal of Nuclear Materials, 179-181, p.441 - 444, 1991/00

https://doi.org/10.1016/0022-3115(91)90119-R
 Times Cited Count：30 Percentile：92.44(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Vacuum system of the JAERI AVF cyclotron

Nakamura, Yoshiteru; Arakawa, Kazuo; Mizuhashi, Kiyoshi; Yokota, Wataru; Kamiya, Tomihiro; Fukuda, Mitsuhiro; Nara, Takayuki; Agematsu, Takashi; Okumura, Susumu; Ishibori, Ikuo; et al.

Proc. of the 8th Symp. on Accelerator Science and Technology, p.194 - 196, 1991/00

no abstracts in English

Journal Articles

Study on 21/4Cr-1Mo steel for high temperature gas cooled reactor; Material characterization of forged low Si21/4Cr-1Mo steel

Oku, Tatsuo; Kodaira, Tsuneo; Fukaya, Kiyoshi; Suzuki, Masahide; *; *; *; *

Nucl. Eng. Des., 119, p.177 - 186, 1990/00

https://doi.org/10.1016/0029-5493(90)90159-U
 Times Cited Count：5 Percentile：52.84(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Recommended practice for small punch(SP) testing of metallic materials; Draft

*; *; *; *; *; *; Oku, Tatsuo; Kodaira, Tsuneo; Fukaya, Kiyoshi; Nishi, Hiroshi; et al.

JAERI-M 88-172, 20 Pages, 1988/09

JAERI-M-88-172.pdf:0.64MB

no abstracts in English

Journal Articles

Evaluation of material degradation by thermal aging in 2 1/4Cr-1Mo steels as a structural material for the VHTR

; ; ;

Nihon Gakujutsu Shinkokai Tainetsu Kinzoku Zairyo Dai-123 Iinkai Kenkyu Hokoku, 27(1), p.11 - 20, 1986/00

no abstracts in English

Journal Articles

International intercomparison on LWR pressure vessel surveilance test data analysis 'PSF Blind Test'

Sekiguchi, Akira*; Nakazawa, Masaharu*; *; ; *; *

Nihon Genshiryoku Gakkai-Shi, 28(1), p.71 - 81, 1986/00

https://doi.org/10.3327/jaesj.28.71
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Stress relaxation of normalized and tempered 2 1/4 Cr-1Mo steel under neutron irradiation

; ; ;

Journal of Nuclear Materials, 132, p.10 - 13, 1985/00

https://doi.org/10.1016/0022-3115(85)90387-3
 Times Cited Count：1 Percentile：24.15(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Few problems Concerning evaluation of degration in Cr-Mo low carbon steel for nuclear structural materials caused by long-term service usage

; ; ;

Nihon Genshiryoku Gakkai-Shi, 27(8), p.722 - 724, 1985/00

https://doi.org/10.3327/jaesj.27.722
 Times Cited Count：0 Percentile：0.33(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Temper and neutron irradiation embrittlement in 2 1/4Cr-1 Mo steels for pressure vessels of high-temperature gas-cooled reactors

; ; ;

Nuclear Technology, 66, p.619 - 629, 1984/00

https://doi.org/10.13182/NT84-A33483
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Jic fracture toughness of nuclear reactor pressure vessel steels at transition and upper shelf regious

; ; ;

Tetsu To Hagane, 61(8), p.1032 - 1039, 1982/00

http://joi.jlc.jst.go.jp/JST.Journalarchive/tetsutohagane1955/68.8_1032

no abstracts in English

JAEA Reports

Development of vibration analysis code for fast breeder reactor core structure (III)

Sasaki, Tsuneo*; Sasaki, Yoichi*; Fujimoto, Shigeru*; Tarutani, Kohei*; Tashiro, Masao*

PNC TJ201 81-26, 168 Pages, 1981/03

PNC-TJ201-81-26.pdf:2.82MB

no abstracts in English

JAEA Reports

Data on Mechanical Properties of 2 1/4C$$_{r}$$$$_{-}$$$$_{1}$$ Mo Steel for the Experimental Very High Temperature Gas-Cooled Reactor

; ; ;

JAERI-M 7948, 50 Pages, 1978/11

JAERI-M-7948.pdf:5.11MB

no abstracts in English

16 (Records 1-16 displayed on this page)
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