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Journal Articles

The Neutron irradiation effect on mechanical properties of HIP joint material

Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Sato, Satoshi; Mori, Kensuke*

Journal of Nuclear Materials, 335(1), p.33 - 38, 2004/10

 Times Cited Count:8 Percentile:48.34(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Microstructural analysis of mechanically tested reduced activation ferritc/martensitic steels

Tanigawa, Hiroyasu; Hirose, Takanori; Ando, Masami; Jitsukawa, Shiro; Kato, Yudai*; Koyama, Akira*

Journal of Nuclear Materials, 307-311(Part1), p.293 - 298, 2002/12

 Times Cited Count:9 Percentile:50.93(Materials Science, Multidisciplinary)

It has been a key issue to get the mechanical understanding of fracture process on microstructure basis, especially on neutron-irradiated materials, but not yet to be understood well enough as for the difficulty of making transmission electron microscope (TEM) thin film sample from mechanical-tested specimen. To solve this technical problem, the focused ion beam (FIB) micro-sampling system was installed to the Research Hot Laboratory of Japan Atomic Research Institute (JAERI), Japan. This system makes it possible to fabricate the TEM specimens from the critical points of mechanical-tested radioactive specimens, such as the crack initiation points of fatigue fracture on neutron irradiated specimen. In this paper, the microstructure of mechanical-tested specimen of Reduced Activation Ferritic/martensitic steels, RAFs are investigated focusing on the helium effects to fatigue fracture.

Journal Articles

Issues to be verified by IFMIF prototype accelerator for engineering validation

Sugimoto, Masayoshi; Imai, Tsuyoshi; Okumura, Yoshikazu; Nakayama, Koichi*; Suzuki, Shohei*; Saigusa, Mikio*

Journal of Nuclear Materials, 307-311(Part2), p.1691 - 1695, 2002/12

 Times Cited Count:2 Percentile:16.55(Materials Science, Multidisciplinary)

International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based intense neutron source for fusion reactor materials development. Each one of the two accelerator modules needs to have a capability to provide the 40MeV/125mA deuteron beam continuously. Although the technology to produce the 7MeV/100mA proton beam is already verified using 350 MHz linac in the past, an engineering study using a prototype is necessary to verify the performance of IFMIF 175 MHz deuteron linac, and Engineering Validation Phase (EVP) is planned for this purpose. Some critical design parameters, like final and transition energies of linacs or RF source characteristics, are needed to be optimised for the prototype. As it is also important to verify the essential component technology, e.g. ion source, RFQ beam matching, rf system components, etc., the present status and expected results of such undergoing verification tests are described. An integrated concept of prototype accelerator is shown as a Japanese proposal for EVP to provide for the international discussion.

Journal Articles

Mechanical properties of HIP bonded W and Cu-alloys joint for plasma facing components

Saito, Shigeru; Fukaya, Kiyoshi*; Ishiyama, Shintaro; Sato, Kazuyoshi

Journal of Nuclear Materials, 307-311(2), p.1542 - 1546, 2002/12

 Times Cited Count:37 Percentile:88.86(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

In situ transmissivity measurements of KU1 quartz in the UV range under 14 Mev neutron irradiation

Nishitani, Takeo; Sugie, Tatsuo; Kasai, Satoshi; Kaneko, Junichi*; Yamamoto, Shin

Journal of Nuclear Materials, 307-311(Part2), p.1264 - 1267, 2002/12

 Times Cited Count:23 Percentile:78.97(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Ab initio study on isotope exchange reactions of H$$_{2}$$ with surface hydroxyl groups in lithium silicates

Nakazawa, Tetsuya; Yokoyama, Keiichi; Grismanovs, V.*; Katano, Yoshio*; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part2), p.1436 - 1440, 2002/12

 Times Cited Count:1 Percentile:9.80(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Cellular automaton model for hydrogen transport dynamics through metallic surface

Shimura, Kenichiro*; Yamaguchi, Kenji; Terai, Takayuki*; Yamawaki, Michio*

Journal of Nuclear Materials, 307-311(2), p.1478 - 1483, 2002/12

 Times Cited Count:2 Percentile:16.55(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Disruption tests on repaired tungsten by CVD coating

Taniguchi, Masaki; Sato, Kazuyoshi; Ezato, Koichiro; Yokoyama, Kenji; Akiba, Masato

Journal of Nuclear Materials, 307-311(Part1), p.719 - 722, 2002/12

 Times Cited Count:18 Percentile:72.74(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Non-destructive testing of CFC monoblock divertor mock-ups

Ezato, Koichiro; Dairaku, Masayuki; Taniguchi, Masaki; Sato, Kazuyoshi; Akiba, Masato

Journal of Nuclear Materials, 307-311(Part1), p.144 - 148, 2002/12

 Times Cited Count:14 Percentile:65.07(Materials Science, Multidisciplinary)

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:28.81(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Neutron irradiation effect on the mechanical properties of type 316L SS welded joint

Saito, Shigeru; Fukaya, Kiyoshi*; Ishiyama, Shintaro; Amezawa, Hiroo; Yonekawa, Minoru; Takada, Fumiki; Kato, Yoshiaki; Takeda, Takashi; Takahashi, Hiroyuki*; Nakahira, Masataka

Journal of Nuclear Materials, 307-311(Part2), p.1573 - 1577, 2002/12

 Times Cited Count:2 Percentile:16.55(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Status of activities on the lithium target in the key element technology phase in IFMIF

Nakamura, Hiroo; Burgazzi, L.*; Cevolani, S.*; Dell'Ocro, G.*; Fazio, C.*; Giusti, D.*; Horiike, Hiroshi*; Ida, Mizuho*; Kakui, Hideo*; Loginov, N.*; et al.

Journal of Nuclear Materials, 307-311(2), p.1675 - 1679, 2002/12

no abstracts in English

Journal Articles

Microstructure and hardness of HIP-bonded regions in F82H blanket structures

Furuya, Kazuyuki; Wakai, Eiichi; Ando, Masami; Sawai, Tomotsugu; Nakamura, Kazuyuki; Takeuchi, Hiroshi; Iwabuchi, Akira*

Journal of Nuclear Materials, 307-311(Part1), p.289 - 292, 2002/12

 Times Cited Count:7 Percentile:43.74(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Evaluation of hardening behavior of ion irradiated reduced activation ferritic/martensitic steels by an ultra-micro-indentation technique

Ando, Masami; Tanigawa, Hiroyasu; Jitsukawa, Shiro; Sawai, Tomotsugu; Kato, Yudai*; Koyama, Akira*; Nakamura, Kazuyuki; Takeuchi, Hiroshi

Journal of Nuclear Materials, 307-311(Part1), p.260 - 265, 2002/12

 Times Cited Count:39 Percentile:89.78(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Water jet flow simulation and lithium free surface flow experiments for the IFMIF target

Ida, Mizuho*; Horiike, Hiroshi*; Akiba, Masato; Ezato, Koichiro; Iida, Toshiyuki*; Inoue, Shoji*; Miyamoto, Seiji*; Muroga, Takeo*; Nakamura, Hideo; Nakamura, Hiroshi*; et al.

Journal of Nuclear Materials, 307-311(Part2), p.1686 - 1690, 2002/12

 Times Cited Count:6 Percentile:39.04(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H

Jitsukawa, Shiro; Tamura, Manabu*; Van der Schaaf, B.*; Klueh, R. L.*; Alamo, A.*; Petersen, C.*; Schirra, M.*; Spaetig, P.*; Odette, G. R.*; Tavassoli, A. A.*; et al.

Journal of Nuclear Materials, 307-311(Part1), p.179 - 186, 2002/12

 Times Cited Count:170 Percentile:99.28(Materials Science, Multidisciplinary)

Reduced activation ferritic/martensitic steel is the primary candidate structural material for ITER Test Blanket Modules and DEMOnstration fusion reactor because of its excellent dimensional stability under irradiation and lower residual activity as compared with the Ni bearing steels such as the austenitic stainless steels. In this paper, microstructural features, tensile, fracture toughness, creep and fatigue properties of a reduced activation martensitic steel F82H (8Cr-2W-0.04Ta-0.1C) are reported before and after irradiation, in addition to the design concept used for development of this alloy. A large number of collaborative test results including those generated under the IEA working group implementing agreements are collected and are used to evaluate the feasibility of use of F82H steel as one of the reference alloys. The effect of metallurgical variables on the irradiation hardening is reviewed and compared with the results obtained from irradiation experiments.

Journal Articles

Exchange of tritium implanted into oxide ceramics for protium by exposure to air vapors at room temperature

Morita, Kenji*; Suzuki, Hironori*; Soda, Kazuo*; Iwahara, Hiroiku*; Nakamura, Hirofumi; Hayashi, Takumi; Nishi, Masataka

Journal of Nuclear Materials, 307-311(2), p.1461 - 1465, 2002/12

 Times Cited Count:2 Percentile:16.55(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Swelling behavior of TIG-welded F82H IEA heat

Sawai, Tomotsugu; Wakai, Eiichi; Tomita, Takeshi; Naito, Akira; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part1), p.312 - 316, 2002/12

 Times Cited Count:20 Percentile:75.72(Materials Science, Multidisciplinary)

TIG-weld joints of the IEA heat of F82H were irradiated by TIARA. Transmission electron microscope (TEM) specimens were prepared by a focused ion beam (FIB) system. TEM specimens were obtained from the heat affected zone (HAZ) and the weld metal. HAZ specimens had typical bi-modal cavity microstructure after 50 dpa at 450$$^{circ}$$C with He/dpa ratio of 10 appmHe/dpa. Larger voids about 30 nm were observed in the tempered side specimen, while the size of voids in the quenched side specimen was less than 15 nm. Ac1 temperature determined by heat-treated base metal is 820$$^{circ}$$C. Cavity growth in specimens tempered at higher temperature was enhanced, while that in cold worked ones is suppressed.

Journal Articles

Phase stability and mechanical properties of irradiated Ti-Al-V intermetallic compounds

Sawai, Tomotsugu; Wakai, Eiichi; Jitsukawa, Shiro; Hishinuma, Akimichi

Journal of Nuclear Materials, 307-311(Part1), p.389 - 392, 2002/12

 Times Cited Count:4 Percentile:28.81(Materials Science, Multidisciplinary)

A Ti-35Al-10V alloy was fabricated from mechanically alloyed powder by a hot-isostatic-pressing. The microstructure consists of $$alpha$$2, $$gamma$$, and $$beta$$ phases. Specimens were irradiated in Japan Research Reactor No. 3 Modified (JRR-3M) up to 3.5 $$times$$ 10$$^{25}$$ n/cm$$^{2}$$ at 400$$^{circ}$$C and 600$$^{circ}$$C. Unirradiated tensile specimens showed total elongation of 3 to 15 % at 400$$^{circ}$$C-tests, while 400$$^{circ}$$C-irradiated or 600$$^{circ}$$C-irradiated specimens showed no plastic deformation before fracture. At 600$$^{circ}$$C tensile tests, unirradiated specimens showed total elongation of more than 60 %, while irradiated ones showed 10 % or less elongation. The low ductility of irradiated specimens suggests embrittlement due to phase decomposition, but electron diffraction using a transmission electron microscope results of irradiated specimens will be also discussed.

Journal Articles

Heat load rest of Be/Cu joint for ITER first wall mock-ups

Uchida, Munenori*; Ishitsuka, Etsuo; Hatano, Toshihisa; Barabash, V.*; Kawamura, Hiroshi

Journal of Nuclear Materials, 307-311(Part2), p.1533 - 1536, 2002/12

 Times Cited Count:3 Percentile:22.96(Materials Science, Multidisciplinary)

no abstracts in English

39 (Records 1-20 displayed on this page)