ITER Control System Model: A full-scale simulation platform for the CODAC infrastructure

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2018-03-01 DOI:10.1016/j.fusengdes.2018.01.060

Martynas Prokopas , Anders Wallander , Bertrand Bauvir , Jorge Sousa

{"title":"ITER Control System Model: A full-scale simulation platform for the CODAC infrastructure","authors":"Martynas Prokopas , Anders Wallander , Bertrand Bauvir , Jorge Sousa","doi":"10.1016/j.fusengdes.2018.01.060","DOIUrl":null,"url":null,"abstract":"<div><p>ITER Control System Model (ICM) is a simulation platform for CODAC that is currently being developed at ITER. CODAC is the conventional control system responsible for operating all plant systems from the 35 member states that are contributing to the ITER development. ICM is a full-scale implementation of CODAC that follows all ITER hardware and software conventions, but does not have any signal interfaces to other components of ITER nor any simulation of physical processes. Instead, it relies on state-based simulators that are used to verify CODAC operation at different stages of ITER execution. ICM currently consists of a single server cubicle that houses all hardware and software required to run a full-scale control system configuration without any dependencies on external servers. With its self-sustaining and isolated nature, ICM is capable of simulating the production stage of ITER. It provides an excellent test environment for various CODAC technologies and validating the interoperability of all the different plant systems across the infrastructure, which will contribute to minimizing the downtime of ITER due to avoidable errors. ICM is also being considered as a potential operator training facility.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"128 ","pages":"Pages 86-89"},"PeriodicalIF":2.0000,"publicationDate":"2018-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/j.fusengdes.2018.01.060","citationCount":"4","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379618300784","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 4

Abstract

ITER Control System Model (ICM) is a simulation platform for CODAC that is currently being developed at ITER. CODAC is the conventional control system responsible for operating all plant systems from the 35 member states that are contributing to the ITER development. ICM is a full-scale implementation of CODAC that follows all ITER hardware and software conventions, but does not have any signal interfaces to other components of ITER nor any simulation of physical processes. Instead, it relies on state-based simulators that are used to verify CODAC operation at different stages of ITER execution. ICM currently consists of a single server cubicle that houses all hardware and software required to run a full-scale control system configuration without any dependencies on external servers. With its self-sustaining and isolated nature, ICM is capable of simulating the production stage of ITER. It provides an excellent test environment for various CODAC technologies and validating the interoperability of all the different plant systems across the infrastructure, which will contribute to minimizing the downtime of ITER due to avoidable errors. ICM is also being considered as a potential operator training facility.

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

ITER控制系统模型:CODAC基础设施的全尺寸仿真平台

ITER控制系统模型(ICM)是目前正在ITER开发的CODAC仿真平台。CODAC是常规控制系统，负责运行来自35个成员国的所有电厂系统，这些国家正在为ITER的发展做出贡献。ICM是CODAC的全面实现，遵循所有ITER硬件和软件约定，但没有任何信号接口到ITER的其他组件，也没有任何物理过程的模拟。相反，它依赖于基于状态的模拟器，用于在ITER执行的不同阶段验证CODAC操作。ICM目前由一个单独的服务器隔间组成，该隔间容纳了运行全面控制系统配置所需的所有硬件和软件，而不依赖于任何外部服务器。ICM具有自我维持和隔离的特性，能够模拟ITER的生产阶段。它为各种CODAC技术提供了一个极好的测试环境，并验证了基础设施中所有不同工厂系统的互操作性，这将有助于最大限度地减少ITER由于可避免的错误而导致的停机时间。ICM也被认为是一个潜在的操作人员培训设施。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文去求助

来源期刊

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.