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JAEA Reports

Development of low decontaminated MOX fuel containing MA I; Influence of Np on sintering behavior and phase separation for (Pu,Np,U) O$$_{2-x}$$

Morimoto, Kyoichi; Kato, Masato; Nishiyama, Motokuni; Endo, Hideo; Kono, Shusaku; Uno, Hiroki*; Tamura, Tetsuya*; Sugata, Hiromasa*

JNC TN8400 2003-011, 32 Pages, 2003/01

JNC-TN8400-2003-011.pdf:0.62MB

MOX fuel containing Neptunium is being developed as candidate fuel for an advanced nuclear fuel recycle. In this report, influence of Np on the sintering behavior, phase separation behavior of MOX fuel pellets and the homogeneity of MOX fuel pellets were evaluated. It was observed that the high Np containing pellets had a low sintered density and the microstructure changes of the pellets during the sintering were slow compared with MOX without Np. The pellets were also analyzed via Ceramography, X-ray diffraction measurement and an electron probe microanalysis. The phase separation behavior of MOX with Np was similar to that of MOX. The homogeneity of the pellet produced with this experiment was acceptable to the fuel specification.

Journal Articles

Low cycle fatigue properties of 8Cr-2WVTa ferritic steel at elevated temperatures

; Fukaya, Kiyoshi; Nishiyama, Yutaka; Suzuki, Masahide; Eto, Motokuni

Journal of Nuclear Materials, 258-263, p.1183 - 1186, 1998/00

 Times Cited Count:38 Percentile:93.16(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Irradiation embrittlement of 2.25Cr-1Mo steel at 400$$^{circ}$$C and its electrochemical evaluation

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni

Journal of Nuclear Materials, 258-263, p.1187 - 1192, 1998/00

 Times Cited Count:4 Percentile:39.76(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Irradiation embrittlement of 21/4Cr-1Mo steel at 400$$^{circ}$$C

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni

JAERI-Research 97-039, 29 Pages, 1997/06

JAERI-Research-97-039.pdf:1.41MB

no abstracts in English

JAEA Reports

Post-irradiation fatigue test of 21/4Cr-1Mo steel for the pressure vessel material of the HTTR

; Fukaya, Kiyoshi; Nishiyama, Yutaka; Suzuki, Masahide; Eto, Motokuni; Omi, Masao; Mimura, Hideaki; Ooka, Norikazu

JAERI-Research 96-028, 33 Pages, 1996/06

JAERI-Research-96-028.pdf:1.85MB

no abstracts in English

JAEA Reports

None

Nishiyama, Motokuni; Kamimura, Katsuichiro; Seki, Masayuki; Tsukada, Tatsuya*; Ishibashi, Fujio; Isaka, Kazuhiko*

PNC TN8410 95-046, 81 Pages, 1995/01

PNC-TN8410-95-046.pdf:4.08MB

None

Journal Articles

Estimation of toughness degradation by microhardness and small punch tests

Suzuki, Masahide; Eto, Motokuni; Nishiyama, Yutaka; Fukaya, Kiyoshi;

Small Specimen Test Techniques; ASTM STP 1204, p.217 - 227, 1993/00

no abstracts in English

Journal Articles

Electrochemical evaluation of thermal aging embrittlement of 21/4Cr-1Mo steel for a nuclear pressure vessel

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni; *

Small Specimen Test Techniques; ASTM STP 1204, p.16 - 26, 1993/00

no abstracts in English

Journal Articles

Development of a miniaturized bulge test(small punch test) for post-irradiation mechanical property evaluation

Eto, Motokuni; *; *; Suzuki, Masahide; Nishiyama, Yutaka; Fukaya, Kiyoshi; Jitsukawa, Shiro

Small Specimen Test Techniques; ASTM STP 1204, p.241 - 255, 1993/00

no abstracts in English

JAEA Reports

DBTT measurement by use of small punch(SP) test

Suzuki, Masahide; Fukaya, Kiyoshi; Nishiyama, Yutaka; Eto, Motokuni

JAERI-M 92-086, 44 Pages, 1992/06

JAERI-M-92-086.pdf:2.79MB

no abstracts in English

Journal Articles

Small specimen test techniques for the evaluation of toughness degradation

Suzuki, Masahide; Eto, Motokuni; Nishiyama, Yutaka; Fukaya, Kiyoshi; *; *

Journal of Nuclear Materials, 191-194, p.1023 - 1027, 1992/00

 Times Cited Count:10 Percentile:68.69(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Evaluation of toughness degradation by small punch (SP) tests for neutron-irradiated 21/4Cr-1Mo steel

Suzuki, Masahide; Eto, Motokuni; Fukaya, Kiyoshi; Nishiyama, Yutaka; Kodaira, Tsuneo; Oku, Tatsuo; ; ; ; *; et al.

Journal of Nuclear Materials, 179-181, p.441 - 444, 1991/00

 Times Cited Count:27 Percentile:92.18(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Electrochemical evaluation of thermal aging embrittlement of 21/4Cr-1Mo steel for the pressure vessel of High Temperature Engineering Test Reactor

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni; *

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 32(2), p.169 - 175, 1991/00

no abstracts in English

Journal Articles

Fracture toughness of a fine-grained nuclear graphite by means of various methods

Eto, Motokuni; Ishiyama, Shintaro; Nishiyama, Yutaka; Oku, Tatsuo*; T.D.Burchell*

Int. Symp. on Carbon New Processing and New Applications; Extended Abstracts,Vol. 1, p.170 - 173, 1990/11

no abstracts in English

14 (Records 1-14 displayed on this page)
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