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neutron imaging and diffraction analysis revealing spatial lithiation phase evolution in an ultra-thick graphite electrodeStrobl, M.*; Baur, M. E.*; Samothrakitis, S.*; Molamud, F.*; Zhang, X.*; Tung, P. K. M.*; Schmidt, S.*; Woracek, R.*; Lee, J.*; Kiyanagi, Ryoji; et al.
Advanced Energy Materials, p.2405238_1 - 2405238_9, 2025/01
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：20 Percentile：60.90(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 
synchrotron X-ray diffraction measurements under controlled conditions and 
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
domain switching extremely improves generating power, and the true energy breakeven with temperature variation is firstly achieved.
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
10
/s. The stability of microstructures under irradiation was also compared with those of electron irradiation using HVEM.
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.
; Mizuta, Shunji; Yoshitake, Tsunemitsu;
The Sixth Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engine, 0 Pages, 2001/00
None
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
Yamakawa, Koichi
Proceedings of International Symposium on Environmental-Conscious Innovative Materials Processing with Advanced Energy Sources (ECOMAP-98), p.215 - 223, 1998/00
no abstracts in English
; Onose, Shoji
Proceedings of International Symposium on Environmental-Conscious Innovative Materials Processing with Advanced Energy Sources (ECOMAP-98), 0 Pages, 1998/00
None
Hayashi, Takumi; Okuno, Kenji
Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, p.205 - 207, 1994/06
no abstracts in English
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
Tsukada, Takashi
Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, 0, p.466 - 471, 1994/00
no abstracts in English
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
