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Journal Articles

Effects of irradiation on mechanical properties of HIP-bonded reduced-activation ferritic/martensitic steel F82H first wall

Furuya, Kazuyuki; Wakai, Eiichi; Miyamoto, Kenji*; Akiba, Masato; Sugimoto, Masayoshi

Journal of Nuclear Materials, 367-370(1), p.494 - 499, 2007/08

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

A partial mock-up of a breeding blanket structure made of F82H steel has been successfully fabricated. In this study, microstructural observation and EDX analysis of the HIP interfaces were performed, and effects of irradiation on mechanical properties of the HIP-bonded region were also examined. Neutron irradiation was performed up to about 2 dpa at about 523 K. After the irradiation, tensile test was performed at temperatures of 295 and 523 K. The HIP interfaces possessed many precipitates, and enriched peak spectrum of chromium was detected from the precipitates. In addition, aspect of the spectrum was qualitatively equivalent to that of M$$_{23}$$C$$_{6}$$ in grain boundaries of F82H steel. In result, the HIP boundary has many M$$_{23}$$C$$_{6}$$ which were generally seen in grain boundaries of F82H steel. Rupture did not occur in the HIP interface. In result, it can be mentioned that bondability is maintained under the irradiation and testing conditions. The strength and elongation of the HIP-bonded region decreased somewhat in comparison with the results of an IEA standard steel.

Journal Articles

Modification of ring tensile test for LWR fuel cladding

Sugiyama, Tomoyuki; Nagase, Fumihisa; Fuketa, Toyoshi

Proceedings of 2005 Water Reactor Fuel Performance Meeting (CD-ROM), p.912 - 932, 2005/10

High burnup fuel cladding can fail due to mechanical interaction with expanding fuel pellet under reactivity initiated accident (RIA) conditions. In order to evaluate the cladding failure limit, investigations to modify ring tensile test have been performed to measure mechanical properties of Zircaloy cladding properly. JAERI developed the test method and geometry minimizing undesirable effects of friction and bending moment in the specimen. Using the modified test method, mechanical properties of unirradiated Zircaloy-4 cladding were evaluated as functions of hydrogen concentration and temperature. For hydrogen concentrations above 700 ppm, obvious increase of ductility is observed with the temperature increase from 300 to 473 K. For hydrogen concentrations below 500 ppm, on the other hand, temperature dependence of ductility is relatively small in the present temperature range from 300 to 573 K.

Journal Articles

Fabrication of SiC fiber reinforced SiC composite by chemical vapor infiltration for excellent mechanical properties

Igawa, Naoki; Taguchi, Tomitsugu; Nozawa, Takashi*; Snead, L. L.*; Hinoki, Tatsuya*; McLaughlin, J. C.*; Kato, Yutai*; Jitsukawa, Shiro; Koyama, Akira*

Journal of Physics and Chemistry of Solids, 66(2-4), p.551 - 554, 2005/02

 Times Cited Count:48 Percentile:82.42(Chemistry, Multidisciplinary)

Silicon carbide is an important engineering ceramic because of its high strength and stability at high temperature and low induced radioactivity after neutron irradiation. Though monolithic SiC is brittle and low toughness, SiC fiber reinforced SiC matrix composites significantly improve these properties and therefore are attractive candidate materials for fusion reactor structural applications. Recently, stoichiometric SiC fibers with superior mechanical properties have been produced. We carried out the optimization of interface and composite fabrication using the chemical vapor infiltration, which is the one of the best techniques to fabricate the SiC composite. The composite with higher density and homogeneous matrix was obtained by the optimization of materials and carrier gas flow rate. The porosity was decreased with increasing the fiber volume fraction. We adopted the carbon or carbon/SiC interface between fiber and matrix and we found that the dependence of interface thickness on the tensile properties was small in the interface thickness from 50 to 300 nm.

Journal Articles

Radiation-modified PTFE as the 21st century material; Development of high function and extreme tenacity for PTFE

Udagawa, Akira*; Ikeda, Shigetoshi*; Yagi, Toshiaki

Hoshasen To Sangyo, (103), p.54 - 58, 2004/09

no abstracts in English

Journal Articles

Development of Be/DSCu HIP bonding and thermo-mechanical evaluation

Hatano, Toshihisa; Kuroda, Toshimasa*; Barabash, V.*; Enoeda, Mikio

Journal of Nuclear Materials, 307-311(2), p.1537 - 1541, 2002/12

 Times Cited Count:4 Percentile:29.2(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Optimization of tensile method and specimen geometry in modified ring tensile test

Kitano, Koji*; Fuketa, Toyoshi; Sasajima, Hideo; Uetsuka, Hiroshi

JAERI-Research 2001-011, 34 Pages, 2001/03

JAERI-Research-2001-011.pdf:2.48MB

no abstracts in English

Journal Articles

High heat flux test of a HIP-bonded first wall panel of reduced activation ferritic steel F-82H

Hatano, Toshihisa; Suzuki, Satoshi; Yokoyama, Kenji; Kuroda, Toshimasa*; Enoeda, Mikio

Journal of Nuclear Materials, 283-287(1), p.685 - 688, 2000/12

 Times Cited Count:20 Percentile:76.44(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Beryllium neutron irradiation study in the Japan Materials Testing Reactor

Ishitsuka, Etsuo; Kawamura, Hiroshi

Fusion Engineering and Design, 41, p.195 - 200, 1998/00

 Times Cited Count:2 Percentile:24.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Radiation effects on fiber-reinforced plastics

Udagawa, Akira

Hihakai Kensa, 45(4), p.270 - 275, 1996/00

no abstracts in English

Journal Articles

Electrical and mechanical properties of coaxial cable for use under high temperature and radioactive conditions, 2

Seguchi, Tadao; Yagi, Toshiaki; *; *; *; *; Nakamura, Hiroshi*; *; *

DEI-94-92, 0, p.37 - 45, 1994/12

no abstracts in English

Journal Articles

High dose irradiation effects of aromatic polymer materials

*; *; Morita, Yosuke; Yagi, Toshiaki; Seguchi, Tadao

Denki Gakkai Yuden, Zetsuen Zairyo Kenkyukai Shiryo; DEI-94-91, 0, p.29 - 36, 1994/12

no abstracts in English

Journal Articles

Life estimation of cable insulating materials by radiation-thermal accelerated aging tests

Yagi, Toshiaki; Seguchi, Tadao; *; *; *

DEI-91-126, p.45 - 53, 1991/12

no abstracts in English

Journal Articles

Radiation resistivity of FRP with low viscous four functional glycidyl amine as a matrix

Udagawa, Akira; Sasuga, Tsuneo; Seguchi, Tadao

DEI-91-134, p.41 - 47, 1991/12

no abstracts in English

Journal Articles

Electron irradiation effects on dynamic viscoelastic properties and crystallization behaviour of aromatic polyimides

Sasuga, Tsuneo

Polymer, 32(9), p.1539 - 1544, 1991/00

 Times Cited Count:16 Percentile:62.83(Polymer Science)

no abstracts in English

JAEA Reports

Studies on radiation resistance of fiber reinforced plastic composites featured by easiness of manufacturing, III; Mechanical properties of high radiation resistant FRP

Udagawa, Akira; Sasuga, Tsuneo; Seguchi, Tadao; *; *; *; *; *; Sonoda, Katsumi*; *

JAERI-M 89-203, 20 Pages, 1989/12

JAERI-M-89-203.pdf:1.24MB

no abstracts in English

JAEA Reports

Election Beam Irradiation Effects on Carbon Fiber Rain Forced PEEK Composite

Sasuga, Tsuneo; Hagiwara, Miyuki; *; *; *; *

JAERI-M 87-048, 29 Pages, 1987/03

JAERI-M-87-048.pdf:1.51MB

no abstracts in English

Journal Articles

Changes of mechanical properties of CFRP by annealing after irradiation with electron beams.

; Sasuga, Tsuneo; Hagiwara, Miyuki; Seguchi, Tadao

EIM-86-133, p.43 - 52, 1986/00

no abstracts in English

Oral presentation

Mechanical property of ITER Central Solenoid (CS) insert coil conductor

Saito, Toru; Ozeki, Hidemasa; Suwa, Tomone; Nabara, Yoshihiro; Kawano, Katsumi; Takahashi, Yoshikazu; Isono, Takaaki; Nunoya, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Science-based integrated models for MOX properties, 1; Relation among lattice constant, coefficient of thermal expansion, mechanical properties and heat capacity

Hirooka, Shun; Kato, Masato; Akashi, Masatoshi; Morimoto, Kyoichi; Matsumoto, Taku

no journal, , 

Sound velocity in MOX pellet at room temperature was measured by ultrasound pulse-echo method. With the newly obtained data of Pu dependence (0-1) and reported data of porosity (0.0543-0.1439) and O/M (1.963-2.000) dependences, equations to evaluate sound velocity with these parameters were derived. Mechanical properties such as Young's modulus can be evaluated from sound velocity. By using Debye model, Debye temperature is evaluated from sound velocity and lattice parameter. Debye temperature leads to heat capacity at constant volume. Sound velocity, lattice parameter, heat capacity at constant volume and coefficient of thermal expansion lead to Gruneisen constant and dilatational term of heat capacity. Suppose that Gruneisen constant is not temperature-dependent, temperature dependence of Young's modulus can be evaluated. Calculated result of Young's modulus of (U$$_{0.8}$$Pu$$_{0.2}$$)O$$_{2}$$ decreased with increasing temperature, which is the same trend as literature.

Oral presentation

R&D of advanced stainless steels for BWR fuel claddings, 3-8; Mechanical properties after neutron irradiation

Takahashi, Katsuhito*; Nozue, Mitsuo*; Miura, Yusuke*; Sakamoto, Kan*; Kimura, Akihiko*; Ukai, Shigeharu*; Yamashita, Shinichiro

no journal, , 

Influence of the neutron irradiation on mechanical properties of FeCrAl ODS stainless steel was estimated as a part of research and development of the accident tolerant fuel. Neutron irradiation of FeCrAl-ODS stainless steel aiming at dose level of 2.6, 3.9, 7.8 and 13 dpa is being carried out at ORNL. In the study, the mechanical properties of FeCrAl-ODS stainless steel were measured up to 2.6 dpa.

22 (Records 1-20 displayed on this page)