LEADER 04391nam 2200649 450 001 9910824371203321 005 20230803210200.0 010 $a3-03826-691-4 035 $a(CKB)3710000000281209 035 $a(EBL)1911003 035 $a(SSID)ssj0001406869 035 $a(PQKBManifestationID)11798814 035 $a(PQKBTitleCode)TC0001406869 035 $a(PQKBWorkID)11402721 035 $a(PQKB)11780185 035 $a(MiAaPQ)EBC1911003 035 $a(Au-PeEL)EBL1911003 035 $a(CaPaEBR)ebr10986832 035 $a(OCoLC)899148556 035 $a(EXLCZ)993710000000281209 100 $a20141201h20142014 uy| 0 101 0 $aeng 135 $aur|n|---||||| 181 $ctxt 182 $cc 183 $acr 200 10$a6th Forum on New Materials $eproceedings of the 6th Forum on New Materials, part of CIMTEC 2014-13th International Ceramics Congress and 6th Forum on New Materials, June 15-19, 2014, Montecatini Terme, Italy. Part B /$fedited by Pietro Vincenzini, World Academy of Ceramics and National Research Council, Italy ; co-edited by Hua-Tay Lin, Oak Ridge National Laboratory, USA, Kevin Fox, Savannah River National Laboratory, USA 210 1$aFaenza, Italy :$cTTP,$d[2014] 210 4$dİ2014 215 $a1 online resource (147 p.) 225 1 $aAdvances in science and technology,$x1662-8969 ;$vvolume 94 300 $aDescription based upon print version of record. 311 $a3-03835-307-8 320 $aIncludes bibliographical references and index. 327 $a6th Forum on New Materials - Part B; Preface; Table of Contents; Chapter 1: Materials for Nuclear Fission and Fusion Technologies; Indian Test Blanket Module in ITER - Development of RAFM Steel and Fabrication Technology; Study on the Creep and Fatigue Properties of CLAM Steel; Behavior at High Temperature of Metallic Liners (Ta, Nb) Used in the Sandwich Cladding Material of the GFR; Utilization Research and Development of Hydride Materials in Fast Reactors; Depleted Uranium as Hydrogen Storage Material; Characterization of SiC Ceramic Tube Prepared by the Combined CVI and CVD Process 327 $aStatus of the Low Enriched Uranium Fuel Development for High Performance Research ReactorsA Microfluidic-Assisted Fabrication of Size-Controlled Porose CeO2 Microspheres as an Analog Production of Nuclear Fuel Beads; Xenon Ion Irradiation Effects on a Ni-Base Ni-17Mo-7Cr Alloy; Chapter 2: Materials for Nuclear Waste Treatment and Disposal; Selective Decontamination and Stable Solidification of Cs-Insoluble Ferrocyanide by Zeolites; Fabrication and Chemical Durability of Ceramic Technetium-Based Pyrochlores and Perovskites as Potential Waste Forms 327 $aBehavior of Fuel and Structural Materials in Severely Damaged ReactorsA New Matrix for Conditioning Chloride Salt Wastes from the Electrorefining of Spent Nuclear Fuel; Adsorption Materials Development for the Separation of Actinides and Specific Fission Products from High Level Waste; Progress at ANSTO on a Synroc Plant for Intermediate-Level Waste from Reactor Production of 99Mo; Review of the Development of the Proposed Yucca Mountain Geologic Repository; RADON Operational Experience in High-Temperature Treatment of Radioactive Wastes 327 $aLeaching Behavior of Salt Wastes Conditioned with Sodalite Blended with Two Different Glass PowdersKeywords Index; Authors Index 330 $aCollection of selected, peer reviewed papers from the 6 th Forum on New Materials, part of CIMTEC 2014-13th International Ceramics Congress and 6 th Forum on New Materials, June 15-19, 2014, Montecatini Terme, Italy. The 18 papers are grouped as follows: Chapter 1: Materials for Nuclear Fission and Fusion Technologies, Chapter 2: Materials for Nuclear Waste Treatment and Disposal. 410 0$aAdvances in science and technology ;$vv. 94. 606 $aCeramics$vCongresses 606 $aCeramic materials$vCongresses 606 $aCeramic engineering$vCongresses 615 0$aCeramics 615 0$aCeramic materials 615 0$aCeramic engineering 676 $a620.14 702 $aVincenzini$b P.$f1939- 702 $aLin$b Hua-Tay 702 $aFox$b Kevin 801 0$bMiAaPQ 801 1$bMiAaPQ 801 2$bMiAaPQ 906 $aBOOK 912 $a9910824371203321 996 $a6th Forum on New Materials$94067930 997 $aUNINA