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Journal Articles

Coefficient of thermal expansion

Oku, Tatsuo*; Baba, Shinichi

Tanso, 2002(202), p.90 - 95, 2002/05

no abstracts in English

Journal Articles

Changes in graphite coefficient of thermal expansion due to fast neutron irradiation and applied stress in the temperature range 300$$^{circ}$$C-1200$$^{circ}$$C

B.J.Marsden*; Arai, Taketoshi; N.McLachlan*

ECN-R--98-005, p.81 - 89, 1998/00

no abstracts in English

Journal Articles

Thermal expansions of NpO$$_{2}$$ and some other actinide dioxides

Yamashita, Toshiyuki; Shirasu, Noriko; Tsuji, Toshihide*; *

Journal of Nuclear Materials, 245(1), p.72 - 78, 1997/00

 Times Cited Count:104 Percentile:98.55(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Preliminary characterization of interlayer for Be/Cu functionally gradient materials; Thermophysical properties of Be/Cu sintered compacts

Saito, Shigeru; *; *; Kawamura, Hiroshi

Functionally Graded Materials 1996, 0, p.215 - 220, 1996/00

no abstracts in English

Journal Articles

Thermal and mechanical properties of beryllium pebbles

Ishitsuka, Etsuo; Kawamura, Hiroshi

Fusion Engineering and Design, 27, p.263 - 268, 1995/00

 Times Cited Count:13 Percentile:76.47(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Evaluation of beryllium pebble produced by rotating electrode method

Ishitsuka, Etsuo; Kawamura, Hiroshi; *; *; Saito, Minoru

JAERI-M 94-032, 28 Pages, 1994/03

JAERI-M-94-032.pdf:1.47MB

no abstracts in English

Journal Articles

Measurement of radial thermal expansivity of carbon fiber

Saito, Tamotsu; Nomura, Shinzo; Imai, Hisashi

Tanso, 146, p.22 - 26, 1991/00

no abstracts in English

JAEA Reports

None

*; *; Miyakawa, Shunichi

PNC TN9430 90-003, 42 Pages, 1990/12

PNC-TN9430-90-003.pdf:1.12MB

None

JAEA Reports

Measurements of physical properties of FBR (Fast Breeder Reactor) structural materials; Part 1 Measurements of physical properties of the rolled steels

*

PNC TN9410 90-094, 80 Pages, 1990/06

PNC-TN9410-90-094.pdf:1.48MB

It is needed for FBR design to know physical properties of the structural materials that will be used for FBR-reactor vessels, -steam generators, and -pipes. In this report, six types of steels that are noted as the structural materials for next steps of FBR are taken up. The six types of steels are as follows ; [SUS 304] [SUS 316 (conventional)] [FBR grade SUS316] [SUS321] [2.25Cr-1Mo steel] [Mod.9Cr-1Mo steel (ASTM A387-91).] Physical properties of the steels are measured on rolled plates made by mills. The measured physical properties are as follows ; [Specific gravity] [Specific heat] [Thermal conductivity] [Thermal expansion] [Young's modulus] [Poisson's ratio.] And also the same kinds of physical properties of S.R. (Stess Relieving) heat treated 2.25Cr-1Mo and Mod.9Cr-1Mo steel plates are measured. Measurement of the physical properties of forgings, pipes, and weld metals of selected types of steels of them will be also carried out in 1990 and all summarized data that will contain the results of this report will be used to determin the criteria design values of the physical properties for the next steps of FBR. (Caution) This report only shows the measurement results of the physical properties of the rolled steel plates but doesn't give the design standards of the physical properties for the next steps of FBR.

Journal Articles

Irradiation-induced property changes of thermally oxidized nuclear graphites

; ;

Journal of Nuclear Materials, 152, p.283 - 288, 1988/00

 Times Cited Count:3 Percentile:39.88(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Journal Articles

Thermal expansion of some pre-stressed nuclear graphites

;

Carbon, 23(1), p.51 - 57, 1985/00

 Times Cited Count:7 Percentile:44.93(Chemistry, Physical)

no abstracts in English

Journal Articles

Effect of oxidation on physical properties of nuclear grade graphites

; ; ;

Journal of Nuclear Materials, 136, p.229 - 237, 1985/00

 Times Cited Count:6 Percentile:64.6(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Irradiation behaviors of nuclear grade graphite in commercial reactor, 1; Dimensional change and thermal expansion

;

Journal of Nuclear Science and Technology, 22(2), p.139 - 146, 1985/00

 Times Cited Count:5 Percentile:65.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

An Approximate relationship between elastic modulus and thermal expansion coefficient for nuclear-grade graphites

;

Journal of Nuclear Materials, 113, p.263 - 267, 1983/00

 Times Cited Count:6 Percentile:88.04(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal expansion of lithium oxide

Kurasawa, T.; ; ; ; ;

Journal of Nuclear Materials, 107(2), p.334 - 336, 1982/00

 Times Cited Count:22 Percentile:96.92(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

None

PNC TN241 81-25VOL2, 113 Pages, 1981/11

PNC-TN241-81-25VOL2.pdf:8.02MB

Journal Articles

Effects of high temperature neutron irradiation on dimension and thermal expansion coefficient of nuclear graphites

; ;

Journal of Nuclear Science and Technology, 18(11), p.863 - 869, 1981/00

 Times Cited Count:4 Percentile:52.55(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The Change in the ratio of thermal expansion coefficient of some nuclear graphites at elevated temperatures

;

Journal of Nuclear Materials, 79(2), p.372 - 378, 1979/00

 Times Cited Count:2

no abstracts in English

23 (Records 1-20 displayed on this page)