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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.
- Format:
- Book
- Conference/Event
- Conference Name:
- Forum on New Materials (6th : 2014 : Montecatini Terme, Italy), issuing body.
- Series:
- Advances in science and technology ; v. 94.
- Advances in science and technology, 1662-8969 ; volume 94
- Language:
- English
- Subjects (All):
- Ceramics--Congresses.
- Ceramics.
- Ceramic materials--Congresses.
- Ceramic materials.
- Ceramic engineering--Congresses.
- Ceramic engineering.
- Physical Description:
- 1 online resource (147 p.)
- Edition:
- 1st ed.
- Place of Publication:
- Faenza, Italy : TTP, [2014]
- Language Note:
- English
- Summary:
- 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.
- Contents:
- 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
- Notes:
- Description based upon print version of record.
- Includes bibliographical references and index.
- Description based on online resource; title from PDF title page (ebrary, viewed December 1, 2014).
- ISBN:
- 3-03826-691-4
- OCLC:
- 899148556
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