Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 1

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

Journal Articles

Development of the ocean forecasting system for Shimokita region

In, Teiji*; Shima, Shigeki*; Nakayama, Tomoharu*; Ishikawa, Yoichi*; Togawa, Orihiko; Kobayashi, Takuya; Kawamura, Hideyuki

Gekkan Kaiyo, 37(9), p.674 - 680, 2005/09

no abstracts in English

Journal Articles

Development and utilization of material database of JAERI

Kaji, Yoshiyuki; Sakino, Takao*; Ugachi, Hirokazu; Tsuji, Hirokazu

"Fukanteki Kanten Karano Kogaku" Shimpojiumu Shiryoshu, p.175 - 178, 2000/11

no abstracts in English

Journal Articles

Present status and future direction of JAERI material performance database (JMPD)

Kaji, Yoshiyuki; Sakino, Takao*; Ugachi, Hirokazu; Tsuji, Hirokazu

Proceedings of 9th German-Japanese Workshop on Chemical Information, p.121 - 124, 2000/00

no abstracts in English

JAEA Reports

Modeling of long-term energy system of Japan

*; Sato, Osamu;

JAERI-Research 99-046, 167 Pages, 1999/07

JAERI-Research-99-046.pdf:8.9MB

no abstracts in English

JAEA Reports

Beryllium data base for in-pile mockup test on blanket of fusion reactor, 1

Kawamura, Hiroshi; *; Ishitsuka, Etsuo; *; Takatsu, Hideyuki

JAERI-M 92-190, 131 Pages, 1992/11

JAERI-M-92-190.pdf:2.83MB

no abstracts in English

JAEA Reports

Materials properties data sheet (No.Q 01); Internal pressure creep properties data on high strength ferritic/martensitic steel in air and in sodim

; ; *; *; Yoshida, Eiichi;

PNC TN9450 92-004, 37 Pages, 1992/06

PNC-TN9450-92-004.pdf:0.78MB

High Strength Ferritic/Martensitic Steel is one of the cardidate core materials for largescale FBR because of excellent resistance to swelling. This report are presented about the internal pressure creep of High Strength Ferritic/Martensitic Steel based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1) Material: High Strength Ferritic/Martensitic Steel Fuel cladding tube ($$phi$$6.5$$times$$0.47.mm$$^{t}$$) (2) Environment: In Air and In Sodium (3) Test temperature: 600 and 650$$^{circ}$$C (4) Hoop stress: 9.48$$sim$$32.43 kgf/㎜$$^{2}$$ (5) Number of data: 13 points

JAEA Reports

Mechanical properties on high Cr-Mo steels at elevated temperature (III); Creep properties of high Cr-Mo steel forgings (250$$sim$$280mm t)

; ; Yoshida, Eiichi;

PNC TN9410 91-099, 106 Pages, 1991/02

PNC-TN9410-91-099.pdf:5.72MB

This stady was performed in order to confirm the influence of sampling method on Creep properties of 9Cr-Mo steel forgings which are promising as candidate materials for steam generator of large scale fast breeder reactor. This results are to be reflected on fundation of materials strength standard. Test materials are four kinds of 9Cr-Mo steel forgings (thickness:250$$sim$$280mmt) such as Mod.9Cr-1Mo (F4, F8 heats), 9Cr-1Mo-Nb-V(G3 heat), 9Cr-2Mo (H6 heat) steels. Results obtained are summarized as follows. (1)In order to evaluation of fundamental material properties, creep-rupture data on three kinds of 9Cr-Mo steel forgings such as Mod.9Cr-1Mo, 9Cr-2Mo and 9Cr-1Mo-Nb-V steels was obtained up to 10,000 hours. (2)The Mod.9Cr-1Mo steel exhibited most excellent creep-rupture strength and the 9Cr-2Mo steel was the worst among the three. (3)The effect of the sampling location of specimens on creep strength was not significant for Mod.9Cr-1Mo steel. But for 9Cr-1Mo-Nb-V steel and 9Cr-2Mo steel, longer creep rupture time was observed with spcimens taken from just below the center of the surface with direction of L, and shorter creep rupture time was observed for those taken from t/2 thickness at the center with direction of Z. (4)Creep strength of 9Cr-2Mo steel was lower than that of Mod.9Cr-1Mo (F4, F8)and 9Cr-1Mo-Nb-V steel. But rupture elongation and reduction of area of 9Cr-2Mo steel was greater than hat of other three materials, irrespective of the sampling location of specimens.

7 (Records 1-7 displayed on this page)
  • 1