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Journal Articles

General properties on compatibility between Be-Ti alloy and SS 316LN

Tsuchiya, Kunihiko; Uchida, Munenori*; Kawamura, Hiroshi

Fusion Engineering and Design, 81(8-14), p.1057 - 1063, 2006/02

 Times Cited Count:11 Percentile:60.27(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Compatibility of lithium oxide single crystals with tungsten sputtered films; The Effect of passivation films

Nasu, Shoichi*; Nagata, Shinji*; Yoshii, Kiichiro*; Takahiro, Katsumi*; Kikuchi, Naoto*; Kusano, Eiji*; Moto, Shintaro*; Yamaguchi, Sadae*; Ohashi, Kentaro*; Noda, Kenji; et al.

Funtai Oyobi Fummatsu Yakin, 52(6), p.427 - 429, 2005/06

no abstracts in English

Journal Articles

Compatibility test between Be$$_{12}$$Ti and Li$$_{2}$$TiO$$_{3}$$

Nakamichi, Masaru; Kawamura, Hiroshi; Uchida, Munenori*

Fusion Engineering and Design, 69(1-4), p.257 - 261, 2003/09

 Times Cited Count:9 Percentile:49.89(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Compatibility between Be$$_{12}$$Ti and SS316LN

Kawamura, Hiroshi; Uchida, Munenori*; Shestakov, V.*

Journal of Nuclear Materials, 307-311(Part1), p.638 - 642, 2002/12

 Times Cited Count:19 Percentile:74.77(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

The Role of cement to be expected in radioactive waste disposal system

Tanaka, Satoru*; Nagasaki, Shinya*; *; *; Muraoka, Susumu; *; *; *; *; *; et al.

Nihon Genshiryoku Gakkai-Shi, 39(12), p.1008 - 1018, 1997/00

 Times Cited Count:3 Percentile:30.37(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Status of beryllium study for the fusion reactor development

Ishitsuka, Etsuo; Kawamura, Hiroshi

Kaku Yugoro, No.4 (Nihon Genshiryoku Gakkai Kaku Yugo Kogakubu Kai Kaiho), 0, p.1 - 11, 1996/02

no abstracts in English

Journal Articles

Reactivity test between beryllium and copper alloys

*; Saito, Shigeru; *; R.Solomon*; Kawamura, Hiroshi

Proc. of 5th Int. Workshop on Ceramic Breeder Blanket Interaction, 0, p.207 - 214, 1996/00

no abstracts in English

JAEA Reports

Compatibility test of blanket structural materials with beryllium sphere in helium gas environment

Kurasawa, Toshimasa; Takatsu, Hideyuki; Seki, Masahiro; *; *

JAERI-Tech 95-011, 24 Pages, 1995/03

JAERI-Tech-95-011.pdf:2.09MB

no abstracts in English

Journal Articles

Tests of ceramic coating made on sheaths of thermocouples for HTTR

Ara, Katsuyuki; ; ; *; *

FAPIG, 0(125), p.19 - 27, 1990/07

no abstracts in English

Journal Articles

Compatibility between several heat resistant alloys and sintered Li$$_{2}$$O in static helium gas environment

Kurasawa, T.; ;

Journal of Nuclear Materials, 92(1), p.67 - 72, 1980/00

 Times Cited Count:5 Percentile:53.45(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Journal Articles

Reaction of several iron and nickel based alloys with sin-tered Li$$_{2}$$O pellets

Kurasawa, T.; ; ; ; *; *

Journal of Nuclear Materials, 80(1), p.48 - 56, 1979/00

 Times Cited Count:13

no abstracts in English

Journal Articles

Reaction of molybdenum and molybdenum-base alloy with sintered Li$$_{2}$$O pellets

; Kurasawa, T.; ; ; *; *

Journal of Nuclear Materials, 80(2), p.249 - 252, 1979/00

 Times Cited Count:4

no abstracts in English

Journal Articles

Mass spectrometric study of the evaporation of LiCrO$$_{2}$$ as a corrosion product in the compatibility experiment of Li$$_{2}$$O pellets with Fe-Ni-Cr alloys

; ; ; ; ; *; *

Journal of Nuclear Materials, 82(2), p.214 - 219, 1979/00

 Times Cited Count:8

no abstracts in English

Journal Articles

Journal Articles

Phase equilibria in system U-Pu-W-C

Ugajin, Mitsuhiro; Abe, Jiro; ; ;

Journal of Nuclear Science and Technology, 13(1), p.36 - 39, 1976/01

 Times Cited Count:0

no abstracts in English

Journal Articles

Thermodynamic activity of carbon in molybdenum-containing uranium carbide

Ugajin, Mitsuhiro

Journal of Nuclear Science and Technology, 12(6), p.381 - 384, 1975/06

 Times Cited Count:0

no abstracts in English

JAEA Reports

Compatibility of Heat Resistant Materials for HTGR,I; Adhesion Test

; ;

JAERI-M 6088, 22 Pages, 1975/03

JAERI-M-6088.pdf:1.63MB

no abstracts in English

Journal Articles

Kinetics of carbon transfer governing compatibility between uranium carbide and stainless steel bonded with sodium

;

Journal of Nuclear Materials, 47(1), p.87 - 94, 1973/01

 Times Cited Count:5

no abstracts in English

Oral presentation

R&D on nitride fuel cycle for MA transmutation to enhance safety and economy, 5; Chemical compatibility between cladding and fuel surrogate materials

Harada, Makoto; Takaki, Seiya; Takano, Masahide

no journal, , 

T91 ferrite steel is considered as cladding of nitride fuels for transmutation of Minor Actinides. In this study, chemical compatibility between cladding and fuel surrogate materials was investigated in two different conditions. One condition was in over melting point of cladding and in short term. The other condition was in predicted operation temperature (773K, 923K, 1023K) and in long term. Surrogate fuel materials were ZrN and Dy$$_{0.3}$$Zr$$_{0.7}$$N, and cladding materials were T91 and SUS316L steel. After the reaction tests, cross sections of specimens were examined by SEM/EDS to characterize the extent of reaction and diffusion. In the melting test, reaction layers didn't exist, but some particles of surrogate fuel materials were observed in cladding layer. In predicted operation temperature test, all specimen had no reaction layers. In conclusion, cladding and fuel surrogate materials have excellent chemical compatibility.

21 (Records 1-20 displayed on this page)