ANALYSIS OF INJECTION MOULDING OF CERAMICS COMPOUNDS BY THE THEORY OF SYSTEMS
The main purpose of this paper is to present the theoretical systemic analysis of injection moulding of ceramic compounds (CIM) with Rophol’s theoretical definitions. The systemic analysis also includes the making of a basic model of CIM. The main principles of CIM and all phenomena connected with the process are represented by means of inputs, outputs and relations. This systemic analysis will be used as a base for easier understanding of this new technology of injection moulding.
Advanced Ceramic Processing and Technology
Advanced Processing Concepts for Increased Ceramic Reliability Processing of Silicon Nitride Powders Wet Forming Processes as a Potential Solution to Agglomeration Problems Processing of Electronic Ceramics Processing of Ceramic Composites Injection Moulding of Fine Ceramics Electrophoretic Deposition as a Processing Route for Ceramics Microwave Processing of Ceramics Thin Film Deposition Processes for Electronic and Structural Ceramics References Index
Physical Ageing of the Research Reactor Core Structural Materials Due to Neutron Irradiation Exposure: a Review
A research reactor (RR) is a  nuclear reactor that has function to generate and utilize neutron flux and radiation ionization for  research purposes and industrial applications. More than 60% of current operating RRs have  been operated for 30 years or more. As the time passes, the functional capabilities of structures,  systems and components (SSCs) of those RRs deteriorate by physical ageing, which can be  caused by neutron irradiation exposure such as irradiation induced dislocation and  microstructural changes. To extend the lifetime and/or to avoid unplanned outages, ageing on  the safety related SSCs of RRs need to be properly managed. An ageing management is a  strategy to engineer, operate, maintenance, and control SSC degradation within acceptable limits. The purpose of this study is to review physical ageing of the core structural materials of  the RRs caused by neutron irradiation exposure. In order to achieve this objective, a wide range  of literatures are reviewed. Comprehensive discussions on irradiation behaviors are limited only  on reactor vessel and core support structure materials made from zirconium and beryllium as  well as their alloys, which are widely used in RRs. It is found that the stability of the mechanical  properties of zirconium and beryllium as well as their alloys was mostly affected by the neutron  fluences and temperatures.