JAEA
  • help
  • PC | SP
  • JP | EN
          
Refine your search：     
Report No.
 - 
Clear All
Search Results: Records 1-20 displayed on this page of 23

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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

http://ci.nii.ac.jp/naid/40001074169

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)