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Journal Articles

Novel electrothermodynamic power generation

Kim, Y.*; Kim, J.*; Yamanaka, Satoru*; Nakajima, Akira*; Ogawa, Takashi*; Serizawa, Takeshi*; Tanaka, Hirohisa*; Baba, Masaaki*; Fukuda, Tatsuo; Yoshii, Kenji; et al.

Advanced Energy Materials, 5(13), p.1401942_1 - 1401942_6, 2015/07

 Times Cited Count:8 Percentile:41.84(Chemistry, Physical)

An innovative electro-thermodynamic cycle based on temporal temperature variations using pyroelectric effect has been presented. Practical energy is successfully generated in both $textit{in-situ}$ synchrotron X-ray diffraction measurements under controlled conditions and $textit{Operando}$ real engine dynamometer experiments. The main generating origin is revealed as a combination of a crystal structure change and dipole change phenomenon corresponds to the temperature variation. In particular, the electric field induced 180$$^circ$$ domain switching extremely improves generating power, and the true energy breakeven with temperature variation is firstly achieved.

Journal Articles

Mechanical properties and microstructural stability of advanced ferritic/martensitic steel under irradiation

Yano, Yasuhide; Yamashita, Shinichiro; Akasaka, Naoaki; Watanabe, Seiichi*; Takahashi, Heishichiro

Proceedings of 9th China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering jointed with CAS-JSPS Core-university Program Seminar on Fusion Materials, System and Design Integration, p.2 - 5, 2007/10

Ferritic/martensitic (F/M) steels are expected to be prospective not only for the long life core material of fast reactors but also for the blanket materials of fusion reactor because of their superior swelling resistance. Japan Atomic Energy Agency has developed a 11Cr-0.5Mo-2W-V, Nb F/M steel (PNC-FMS) for core materials of next fast reactor. In order to evaluate the effect of structural change due to irradiation on mechanical properties of PNC-FMS, neutron irradiations were carried out between 773 and 1013 K to doses of from 11 to 102 dpa in JOYO reactor. Post irradiation tensile tests were performed at 773-1013 K with a strain rate of 0.5$$times$$10$$^{-4}$$/s. The stability of microstructures under irradiation was also compared with those of electron irradiation using HVEM.

Journal Articles

Effects of irradiation and water temperatures on IASCC susceptibility of stainless steels

Miwa, Yukio; Tsukada, Takashi

Proceedings of 8th Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering, p.161 - 168, 2004/10

Irradiation assisted stress corrosion cracking (IASCC) is one of the environmental degradation problems of in-core structural materials for light water reactors. The effects of irradiation and water temperatures on the IASCC were studied using type 316(LN) stainless steels irradiated at 333-673 K to 1.1-16 dpa. IASCC did not occur at 513 K in oxygenated water for specimens irradiated below 573 K to 1.1-16 dpa, but IASCC occurred above 533 K in oxygenated water for all specimens. The irradiation temperature had a strong influence on IASCC susceptibility at 513 K in oxygenated water, so that the irradiation temperature dependence was compared with the temperature dependence of other radiation-induced phenomena.

Journal Articles

High Temperature Capability of ODS Martensitic Steel Claddings

; Mizuta, Shunji; Yoshitake, Tsunemitsu; *

The Sixth Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engine, 0 Pages, 2001/00

None

Journal Articles

Progress of technology R&D in JAERI for the experimental reactor

Matsuda, Shinzaburo

Abstracts of 5th Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering, P. 4, 1998/11

no abstracts in English

Journal Articles

Thermomechanical Properties of B4C Based Composites

; Onose, Shoji

Proceedings of Environment-Conscious Innovative Materials Processing with Advanced Energy Sources (ECOMAP '98), 0 Pages, 1998/00

None

Journal Articles

Development of compact tritium confinement system using gas separation membrane

Hayashi, Takumi; Okuno, Kenji

Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, p.205 - 207, 1994/06

no abstracts in English

Journal Articles

Summary of benchmark experiments for simulation of fusion reactors using an annular blanket with a line D-T source

Maekawa, Hiroshi; Oyama, Yukio; M.A.Abdou*

Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, 0, p.235 - 246, 1994/00

no abstracts in English

Journal Articles

Irradiation assisted stress corrosion cracking (IASCC) studies in Japan

Tsukada, Takashi

Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, 0, p.466 - 471, 1994/00

no abstracts in English

Journal Articles

Behavior of newly-developed radiation resistant optical fibers in a variety of irradiation environments

Kakuta, Tsunemi; Shikama, Tatsuo*; *; ; *; *; Shamoto, N.*

Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, 0, p.229 - 234, 1994/00

no abstracts in English

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