• Journal of the Korea Institute of Information and Communication Engineering
• /
• v.14 no.2
• /
• pp.521-533
• /
• 2010

The OSGi framework is a java-based service platform that can be remotely managed, providing an application life cycle management model, a service registry and an execution environment. Based on the framework, various OSGi layers, APIs, and services have been defined. A bundle is an application that can be executed in the OSGi framework, deployed through a bundle repository. Usually, bundles in the repository are accessible via a designated web page. Unfortunately, the current bundle repositories do not provide any kind of group access services and dynamic bundle installation and deployment. In this paper, we describe a WebDAV-Based OSGi bundle repository named WOBR, which supports effective group-based accesses. WOBR is composed of a WOBR bundle repository, a management bundle and an access bundle that interact with the bundle repository. The management bundle is for configuration of the WOBR bundle repository, managing group access facility to the repository. The access bundle provides access to the repository and search mechanism for the bundles. Additionally, it provides the life cycle management of the installed bundles on the local environment.

• Transactions of the Korean Society of Mechanical Engineers B
• /
• v.40 no.12
• /
• pp.815-824
• /
• 2016

The fuel assembly for pressurized water reactor (PWR) consists of fuel rod bundle, spacer grid and bottom/top end fittings. The cooling water in high pressure and temperature is introduced in lower plenum of reactor core and directed to upper plenum through the subchannel which is formed between the fuel rods. The main thermal-hydraulic performance parameters for the PWR fuel are pressure drop and critical heat flux in normal operating condition, and quenching time in accident condition. The Korea Atomic Energy Research Institute (KAERI) has been developing an advanced PWR fuel, dual-cooled annular fuel and accident tolerant fuel for the enhancement of fuel performance and the localization. For the key thermal-hydraulic technology development of PWR fuel, the KAERI LWR fuel team has conducted the experiments for pressure drop, turbulent flow mixing and heat transfer, critical heat flux(CHF) and quenching. The computational fluid dynamics (CFD) analysis was also performed to predict flow and heat transfer in fuel assembly including the spent fuel assembly in dry cask for interim repository. In addition, the research cooperation with university and nuclear fuel company was also carried out to develop a basic thermal-hydraulic technology and the commercialization.