6th Forum on New Materials : proceedings 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 / edited 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.
Material type:
TextSeries: Advances in science and technology (Faenza, Italy) ; v. 94.Publisher: Faenza, Italy : TTP, [2014]Copyright date: ©2014Description: 1 online resource (147 pages) : illustrations (some color)Content type: - text
- computer
- online resource
- 9783038266914
- 3038266914
- 6th Forum on New Materials. Part B.
- Ceramics -- Congresses
- Ceramic materials -- Congresses
- Ceramic engineering -- Congresses
- Céramique industrielle -- Congrès
- Matériaux céramiques -- Congrès
- Génie céramique -- Congrès
- TECHNOLOGY & ENGINEERING -- Engineering (General)
- TECHNOLOGY & ENGINEERING -- Reference
- Ceramic engineering
- Ceramic materials
- Ceramics
- 620.14
- TP786 .F67 2014eb
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Electronic-Books
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OPJGU Sonepat- Campus | E-Books EBSCO | Available |
Includes bibliographical references and index.
Online resource; title from PDF title page (ebrary, viewed December 1, 2014).
6th 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.
Status 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.
Behavior 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.
Leaching Behavior of Salt Wastes Conditioned with Sodalite Blended with Two Different Glass PowdersKeywords Index; Authors Index.
Collection 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.
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