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Author China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering (7th : 2002 : Lanzhou Shi, China)

Title Materials for advanced energy systems and fission & fusion engineering : proceedings of the Seventh China-Japan Symposium : Lanzhou, China, 29 July-2 August, 2002 / edited by Z.G. Wang, Z.Y. Zhu, G.M. Jin ; Institute of Modern Physics, CAS, China
Published New Jersey : World Scientific, ©2003


Description 1 online resource (443 pages) : illustrations
Contents Status of the fusion research activities at SWIP / C.H. Pan [and others] -- Japanese contribution to the ITER engineering design activities and preparation for the ITER construction phase / S. Matsuda -- Research on SiC/C plasma-facing functionally graded materials (FGM) in China / C.C. Ge, W.B. Cao and A.H. Wu -- Advanced nuclear fuel development in Japan / M. Yamawaki -- A study of behavior of inert gases in some candidate materials for fusion reactors / C.H. Zhang [and others] -- Activation calculation for a fusion experimental breeder, FEB-E / K.M. Feng -- Safety design of support structure and requirements for cryogenic structural materials in fusion magnet system / A. Nishimura -- Quantum chemical calculation on the interaction of hydrogen isotopes with materials for energy system / S. Tanaka and H. Tanigawa -- Plasma facing materials in LHD and collaboration activities with China / N. Noda [and others] -- High power density blanket design study for fusion reactors / J.H. Huang, Y.K. Zhu and P. Zh. Deng -- Study on conceptual design of tritium production reactor based on ST / K.H. He and J.H. Huang -- Tritium decontamination from various materials (experiment with used tritium gas cylinder) / M. Nishikawa, T. Takeishi and K. Katayama -- In-reactor tritium release behavior from molten lithium-tin alloy as a liquid metal breeder / Y. Kang, T. Terai and Y. Nitta -- Plasma surface interaction studies on low activation materials / T Hino [and others] -- Nondestructive measuring technique of tritium retained on/in plasma-facing materials / M. Matsuyama, K. Yoshida and K. Watanabe -- Analysis of the radiation shield of HT-7U tokamak / Q.Y. Huang and Y.X. Chen -- Analysis of MHD pressure drop in the packed pebble bed-based blanket for the FDS / H.Y. Wang, Y.C. Wu and X.X. He -- Fission reactor irradiation tests of bolometer / M. Narui [and others] -- Thermal performance of TF coils case in HT-7U in the case of plasma disruption / B.J. Xiao -- Microstructure changes of plasma spraying tungsten coatings on CFC after different temperature annealing / X. Liu [and others] -- High power density effects on the key component design in dual-cooled transmutation blanket for FDS / Y. Ke and Y.C. Wu -- Tokamak physics design of fusion driven subcritical system / B. Wu -- Development and application of MCNP auto-modeling tool: MCAM 2.0 / X.P. Liu [and others] -- Leakage rate of combined hemispherical shells with D-T neutrons / Y. Chen [and others] -- Thermal fatigue study of W/Cu joint / F. Zhang [and others] -- Laser confocal microscope measurement of the in-beam fatigue fracture surface for F82H steel / Y. Murase, J. Nagakawa and N. Yamamoto -- Flow analyses of liquid metal first wall / G. Hu and J.H. Huang
Effective core potentials study on lanthanide hydrides / X.G. Long [and others] -- The first principle study on ZrV[symbol] system / S.M. Peng [and others] -- Behaviors of cascade damage structure under electron irradiation and annealing / H. Takahashi [and others] -- Phase transformation of TiNi shape memory alloy under electron irradiation / F.R. Wan, X.T. Zu and L.M. Wang -- Dependence of radiation damage in stainless steel on irradiation temperature and dose / S.Y. Zhu [and others] -- Surface damage induced by swift heavy ions in HOPG / J. Liu [and others] -- Positron annihilation study for electronic structrure of Cu precipitates in dilute Fe-Cu alloys / Z. Tang [and others] -- MeV C-ion induced grain boundary crack at 316L SS surface / Z.G. Wang [and others] -- Calculation of diffusion barriers for helium atom in vanadium by effective medium theory / Z.C. Wu [and others] -- Effects of applied stress on microstructural evolution in highly crystalline SiC fiber / T. Shibayama [and others] -- Interfacial shear strength and its effects on the mechanical properties of Hi-Nicalon/CVI-SiC matrix composites / W. Yang [and others] -- Damage of SiO[symbol] glass induced by high energy Ar ions / Z.Y. Zhu [and others] -- Formation and annihilation of [symbol]Al in SiC composites in fusion neutron rnvironment / T. Noda [and others] -- The modification potential in implanted polyimide / Y.M. Sun [and others] -- Studies on the spatial homogeneity and flexural strength of several SiC fiber-reinforced CVI-SiC matrix composites / H. Araki [and others] -- Study on retention and chemical states of implanted deuterium into boron thin film / H. Kodama [and others] -- Hydrogen behavior on the surface of SS-304 and Fe for cooling pipe / Y. Oya [and others] -- Effect of helium on the irradiation damage behaviour in HAZ of low activation Fe-Cr-Mn(W, V) alloy with higher performance / B.F. Hu, H. Kinoshita and H. Takahashi -- Investigation on the surface topography of amorphous alloys implanted with helium ions / M.D. Hou [and others] -- Fatigue performance of a CuCrZr alloy for high heat flux applications in fusion systems / M.M. Li and J.F. Stubbins -- Evolution of small dislocation loop during deformation / Y.M. Yang, N. Sekimura and H. Abe -- Development of candidate plasma facing materials for steady state operation of the HT-7U superconducting tokamak / J.L. Chen [and others] -- Amorphization in ceramic materials under fission fragment bombardment / G. Szenes -- Hydrogen embrittlement of a V4Cr4Ti alloy / J.M. Chen [and others] -- Irradiation effect of HT-9 steel induced by 510 MeV carbon ions / Y.F. Jin [and others] -- Effect of dislocation on the irradiation creep of SUS 316L / K. Ueno [and others]
Summary In this proceedings volume, the following topics are discussed: systems and design; blanket and first wall technology of fission and fusion reactors; fission and fusion materials; radiation damage analysis; calculation codes; databases
Bibliography Includes bibliographical references
Notes Print version record
Subject Power resources -- Congresses
Total energy systems (On-site electric power production)
Heat resistant alloys -- Congresses
TECHNOLOGY & ENGINEERING -- Power Resources -- Nuclear.
Heat resistant alloys
Power resources
Total energy systems (On-site electric power production)
Genre/Form Conference papers and proceedings
Form Electronic book
Author Wang, Z. G
Zhu, Z. Y
Jin, G. M., 1943-
Institute of Modern Physics, CAS, China
ISBN 9789812705198