Towards the DTT configuration management platform architecture

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Francesca Giovanna Lanzotti , Andrea Zoppoli , Giuseppe Di Gironimo
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引用次数: 0

Abstract

Effective project management methods, tools and working practices shall be applied to facilitate the communication and collaboration among the different institutions involved in the Divertor Tokamak Test (DTT) project. This paper deals with the definition of the configuration management platform architecture enabling technical integration of the DTT system. The first step consists in the identification of main requirements the platform should satisfy, considering the multidisciplinary domains and the geographically dispersed working teams characterizing the nuclear fusion sector and the maturity level of the specific project. Main characteristics of the most advanced Product Lifecycle Management (PLM) tools are identified, their limits and benefits are evaluated, and the suitable PLM platform is selected, satisfying the DTT project needs. The definition of the architecture of the configuration management platform for the DTT project aims at implementing the DTT assembly model in a unique environment able to exchange models and data even developed outside the platform ensuring the congruence of the design, the traceability of design changes and the adoption of a proper Systems Engineering approach.

建立数字地面电视配置管理平台架构
应采用有效的项目管理方法、工具和工作惯例,促进参与 "憩息器托卡马克试验" (DTT)项目的不同机构之间的交流与合作。本文介绍如何定义配置管理平台架构,实现 DTT 系统的技术集成。考虑到核聚变领域的多学科领域和分散在各地的工作团队,以及具体项目的成熟度,第一步是确定平台应满足的主要要求。确定最先进的产品生命周期管理(PLM)工具的主要特点,评估其局限性和优势,并选择合适的 PLM 平台,以满足 DTT 项目的需求。为 DTT 项目定义配置管理平台架构的目的是在一个独特的环境中实施 DTT 装配模型,该环境甚至能够交换在平台之外开发的模型和数据,确保设计的一致性、设计变更的可追溯性以及采用适当的系统工程方法。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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