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JAEA Reports

Influence of hydrogen absorption and neutron irradiation on mechanical properties of zircaloy-4 and MDA (Joint research)

Nagase, Fumihisa; Sugano, Mitsuteru*; Ozawa, Masaaki*; Komatsu, Kazushi*; Furuta, Teruo*

JAERI-Research 2001-008, 61 Pages, 2001/03

JAERI-Research-2001-008.pdf:2.62MB

no abstracts in English

Journal Articles

Thermal diffusivity of high burnup UO$$_{2}$$ pellet

Nakamura, Jinichi; Uchida, Masaaki; Uetsuka, Hiroshi; Furuta, Teruo

IAEA-TECDOC-1036, 0, p.127 - 138, 1998/08

no abstracts in English

Journal Articles

Thermal diffusivity of high burnup UO$$_{2}$$ pellet irradiated at HBWR

Nakamura, Jinichi; Furuta, Teruo; Sukegawa, T

HPR-347, 12 Pages, 1996/00

no abstracts in English

JAEA Reports

Fission gas release during power change; Re-irradiation test of LWR fuel rod at JMTR

Nakamura, Jinichi; Endo, Yasuichi; ; ; Furuta, Teruo

JAERI-Research 95-083, 38 Pages, 1995/11

JAERI-Research-95-083.pdf:1.42MB

no abstracts in English

JAEA Reports

Status and task of the study on the hydrogen embrittlement of zirconium alloys

Nagase, Fumihisa; *; Komatsu, Kazushi*; Furuta, Teruo

JAERI-Review 95-012, 122 Pages, 1995/08

JAERI-Review-95-012.pdf:4.42MB

no abstracts in English

Journal Articles

Oxide layer-thickness measurement on fuel cladding for high burnup HBWR fuel rods using eddy current method (Non-destructive examination)

Nakata, Masahito; Amano, Hidetoshi; ; Nishi, Masahiro; Nakamura, Jinichi; Furuta, Teruo; ;

HPR-345, 0, 9 Pages, 1995/00

no abstracts in English

Journal Articles

Post-irradiation examination of high burnup HBWR fuel rods at JAERI

Nakamura, Jinichi; Uetsuka, Hiroshi; Kono, Nobuaki; ; ; Furuta, Teruo

HPR-345 (Vol. II), 0, 13 Pages, 1995/00

no abstracts in English

JAEA Reports

Basic safety research for high burnup fuels in light water reactors

Furuta, Teruo

JAERI-Tech 94-027, 152 Pages, 1994/11

JAERI-Tech-94-027.pdf:6.45MB

no abstracts in English

JAEA Reports

Conceptual design of backend technology R & D facility for TRU recycle in the future cycle system

Fujine, Sachio; Usuda, Shigekazu; Morita, Yasuji; Yoshida, Zenko; ; Furuta, Teruo; Tone, Tatsuzo; *; Nishimura, Kenji*; *

JAERI-M 93-211, 87 Pages, 1993/11

JAERI-M-93-211.pdf:2.42MB

no abstracts in English

JAEA Reports

Investigation of research and development subjects for the very high burnup fuel; Development of fuel pellet

Hayashi, Kimio; Amano, Hidetoshi; ; Furuta, Teruo; Nagase, Fumihisa; Suzuki, Masahide

JAERI-M 93-100, 175 Pages, 1993/06

JAERI-M-93-100.pdf:5.41MB

no abstracts in English

JAEA Reports

Investigation of research and development subjects for very high burnup fuel; Development of fuel cladding materials

Nagase, Fumihisa; Suzuki, Masahide; Furuta, Teruo; ; Hayashi, Kimio; Amano, Hidetoshi

JAERI-M 93-104, 116 Pages, 1993/05

JAERI-M-93-104.pdf:3.64MB

no abstracts in English

JAEA Reports

Design study of fuel fabrication and test facility and post-irradiation examination facility for the development of new type fuels

Amano, Hidetoshi; ; Yamahara, Takeshi; ; Furuta, Teruo

JAERI-M 93-103, 75 Pages, 1993/05

JAERI-M-93-103.pdf:2.35MB

no abstracts in English

Journal Articles

Present status of LWR fuel cladding development

Furuta, Teruo

Genshiryoku Kogyo, 39(5), p.44 - 49, 1993/00

no abstracts in English

JAEA Reports

Interaction between silver and zircaloy-4 at high temperatures

Nagase, Fumihisa; ; Uetsuka, Hiroshi; Furuta, Teruo

JAERI-M 92-179, 31 Pages, 1992/11

JAERI-M-92-179.pdf:2.66MB

no abstracts in English

JAEA Reports

Current status and perspectives of study of zircaloy cladding waterside corrosion in LWRs

Suzuki, Motoe; Furuta, Teruo

JAERI-M 92-162, 57 Pages, 1992/11

JAERI-M-92-162.pdf:1.97MB

no abstracts in English

Journal Articles

Fuel Reliability Laboratory

Furuta, Teruo

Kaku Nenryo, (17), p.17_44 - 17_45, 1992/06

no abstracts in English

JAEA Reports

Interaction between silver-indium-cadmium control-rod alloy and zircaloy at high temperatures

Nagase, Fumihisa; ; Uetsuka, Hiroshi; Furuta, Teruo

JAERI-M 92-001, 28 Pages, 1992/02

JAERI-M-92-001.pdf:2.39MB

no abstracts in English

JAEA Reports

Design study on a very long life light water power reactor core

Naito, Yoshitaka; Furuta, Teruo; Ichikawa, Hiroki; Takano, Hideki

JAERI-M 91-028, 151 Pages, 1991/03

JAERI-M-91-028.pdf:4.53MB

no abstracts in English

JAEA Reports

Investigation on Halden LWR ramp test by means of FEMAXI-III code(PWR version)

Nakamura, Jinichi; *; Furuta, Teruo; *

JAERI-M 91-027, 36 Pages, 1991/03

JAERI-M-91-027.pdf:1.03MB

no abstracts in English

Journal Articles

Some investigation on Halden LWR ramp test by FEMAXI-III(PWR version)

Nakamura, Jinichi; Furuta, Teruo; *; *

HPR-339/13, 22 Pages, 1991/00

no abstracts in English

23 (Records 1-20 displayed on this page)