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Journal Articles

Design and technology development of solid breeder blanket cooled by supercritical water in Japan

Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.

Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12

 Times Cited Count:101 Percentile:93.45(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Effective thermal conductivity measurement of the candidate ceramic breeder pebble beds by the hot wire method

Enoeda, Mikio; Ohara, Yoshihiro; Roux, N.*; Ying, A.*; Pizza, J.*; Malang, J.*

Fusion Technology, 39(No.2 Part.2), p.612 - 616, 2001/03

no abstracts in English

JAEA Reports

A study on properties of uranium oxide using band theory

Tejima, Shogo

JNC TN8400 2000-029, 54 Pages, 2000/10

JNC-TN8400-2000-029.pdf:1.32MB

This report describes the study done by the author as a postdoctoral research associate at Japan Nuclear Cycle Development Institute. This report is divided into three parts: construction of a relativistic band calculation formalism based on the density functional theory, using this method, investigation of the electrical properties for ferromagnetic UGe$$_{2}$$ and antiferromagnetic UO$$_{2}$$. (1)A relativistic band calculation (RBC) method. Band calculations for the s, p, and d electric structure have been developed well in the practical application and theoretical study. But band calculation method treating magnetic 5f electrons as actinide compounds are complicated and needed relativistic approach, so it is behind with the study of the 5f system. In this study we construct the relativistic band calculationformalism valid for magnetic 5f electrons. (2)Electric properties of UGe$$_{2}$$. The actinide compounds UGe$$_{2}$$ is ferromagnetic, so the theoretical analysis is not well yet. The electric structure and fermi surface of UGe$$_{2}$$ are analyzed using the RBC. The theoretical results show that UGe$$_{2}$$ is heavy electron with the 5f character and are agreement with experimental one. (3)Electric structure of nuclear fuel UO$$_{2}$$. It is important to understand the mechanism of the thermal conductivity of nuclear fuel as antiferromagnetic UO$$_{2}$$. The UO$$_{2}$$ band calculation reflecting the thermal properties, into account of relativistic effect, have not done yes. So using the RBC the detailed electric structure of UO$$_{2}$$ are obtained.

JAEA Reports

The evaluation of material base standard of ODS ferritic stainless steel core component for fast breeder reactors

Mizuta, Shunji; ;

JNC TN9400 2000-048, 28 Pages, 2000/04

JNC-TN9400-2000-048.pdf:0.64MB

ODS (Oxide Dispersion Strengthened) ferritic-martainsitic steels are one of the most prospective cladding materials for advanced fast breeder reactors, since they are expected to have excellent swelling resistance and superior high temperature strength due to the finely distributed stable oxide particles(Y$$_{2}$$O$$_{3}$$). Properties and the tentative strength equations for ODS ferritic-martainsitic were proposed on the basis of the latest data to apply to the feasibility study of the sodium coolant MOX fuel plant. The items of equations are follows. (1)creep rupture strength (2)correction factor of creep rupture strength (in Na and in reactor) (3)outer surface eorrosion (Na) (4)inner surface corrosion (in MOX fuel pin) (5)thermal conductivity

JAEA Reports

None

Yamanaka, Shinsuke*; Abe, Kazuyuki

JNC TY9400 2000-004, 78 Pages, 2000/03

JNC-TY9400-2000-004.pdf:2.39MB

no abstracts in English

Journal Articles

Experimental research on nitride fuel cycle in JAERI

Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa; Shirai, Osamu; Suzuki, Yasufumi

Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 8 Pages, 1999/00

no abstracts in English

Journal Articles

Thermal conductivity of actinide mononitride solid solutions

Arai, Yasuo; Nakajima, Kunihisa; Suzuki, Yasufumi

Journal of Alloys and Compounds, 271-273, p.602 - 605, 1998/00

 Times Cited Count:16 Percentile:68.02(Chemistry, Physical)

no abstracts in English

Journal Articles

Thermophysical and thermodynamic properties of actinide mononitrides and their solid solutions

Suzuki, Yasufumi; Arai, Yasuo

Journal of Alloys and Compounds, 271-273, p.577 - 582, 1998/00

 Times Cited Count:39 Percentile:85.51(Chemistry, Physical)

no abstracts in English

Journal Articles

Report on international meeting 「International Seminar on Thermal Performance of (high burnup) LWR Fuel」

Nakamura, Jinichi

Kaku Nenryo, (29), P. 15, 1998/00

no abstracts in English

Journal Articles

Thermal diffusivity measurement of high burnup UO$$_{2}$$ pellet

Nakamura, Jinichi; Uchida, Masaaki; Uetsuka, Hiroshi; Kodaira, Tsuneo; Yamahara, Takeshi;

Proc. of Int. Topical Meeting on LWR Fuel Performance, 0, p.499 - 506, 1997/03

no abstracts in English

Journal Articles

Density dependence of thermal conductivity of SiC/SiC composites fabricated by CVI

Nakano, Junichi; Yamada, Reiji

Proc. of 2nd IEA/JUPITER Joint Int. Workshop on SiC/SiC Ceramic Composites for Fusion Applications, p.64 - 67, 1997/00

no abstracts in English

Journal Articles

Properties of neptunium-plutonium mixed nitride solid solutions

Arai, Yasuo; Nakajima, Kunihisa;

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.347 - 357, 1997/00

no abstracts in English

Journal Articles

Recent progress of nitride fuel development in JAERI; Fuel property, irradiation behavior and application to dry reprocessing

Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa; Suzuki, Yasufumi

Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 1, p.664 - 669, 1997/00

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

Journal Articles

Ceramic breeding blanket development for experimental fusion reactor in JAERI

Kurasawa, Toshimasa; Takatsu, Hideyuki; Sato, Satoshi; Mori, Seiji*; Hashimoto, T.*; Nakahira, Masataka; Furuya, Kazuyuki; Tsunematsu, Toshihide; Seki, Masahiro; Kawamura, Hiroshi; et al.

Fusion Engineering and Design, 27, p.449 - 456, 1995/00

 Times Cited Count:7 Percentile:59.17(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Research on actinide mononitride fuel

Arai, Yasuo; ; Handa, Nuneo

Global 1995, Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems,Vol. 1, 0, p.538 - 545, 1995/00

no abstracts in English

Journal Articles

Properties of MOX fuels

Nihon Genshiryoku Gakkai-Shi, 37(10), p.919 - 921, 1995/00

no abstracts in English

Journal Articles

Thermal diffusivity of neutron-irradiated carbon-carbon composites

Matsuo, Hideto; Nagasaki, Takanori

Journal of Nuclear Materials, 217, p.300 - 303, 1994/00

 Times Cited Count:1 Percentile:17.88(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal conductivity of neptunium mononitride from 740 to 1600K

Arai, Yasuo; Okamoto, Yoshihiro;

Journal of Nuclear Materials, 211, p.248 - 250, 1994/00

 Times Cited Count:15 Percentile:85.23(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

The Effect of oxygen impurity on the characteristics of uranium and uranium-plutonium mixed nitride fuels

Arai, Yasuo; *; Omichi, Toshihiko

Journal of Nuclear Materials, 202, p.70 - 78, 1993/00

 Times Cited Count:30 Percentile:91.53(Materials Science, Multidisciplinary)

no abstracts in English

51 (Records 1-20 displayed on this page)