{"title":"The design progress of neutral beam duct liner remote handling tool in ITER blanket remote handling system","authors":"Tomoyuki ITO, Yuto NOGUCHI, Nobukazu TAKEDA","doi":"10.1016/j.fusengdes.2025.115217","DOIUrl":null,"url":null,"abstract":"<div><div>This paper presents the system design of the Neutral Beam Duct Liner (NBDL) remote handling system for the ITER experimental fusion reactor. All maintenance inside the Vacuum Vessel (VV), such as maintenance of Blanket Modules, Divertors, and NBDL panels, needs to be performed remotely since the environment inside the VV will become highly radioactive once fusion operation begins. The NBDL Remote Handling (NBDL-RH) system is a subsystem of the Blanket Remote Handling System (BRHS) and is designed to be handled by the Vehicle Manipulator (VMNP) of BRHS. One of the key design challenges of this work is to develop a configuration that enables the NBDL-RH Tool to operate inside the Neutral Beam Duct independently from the VMNP, while also achieving operational efficiency. The NBDL-RH system was configured to consists of the NBDL-RH Tool, which functions within the Neutral Beam Duct; utility subsystem such as power supply and signal transmission; in-porting and out-porting subsystem for transporting the NBDL-RH Tool, in its various design configurations, into and out of the VV by means of cask transfers; and another supporting subsystem. To this end, the NBDL-RH Tool has been conceptually designed in a modular configuration incorporating a Tool Changer. This approach reduced the number of cask transfers by approximately one-third compared to a system without a Tool Changer. Furthermore, the modular configuration minimized the amount of manual reassembly work required in the Hot Cell Facility.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115217"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625004132","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: 0
Abstract
This paper presents the system design of the Neutral Beam Duct Liner (NBDL) remote handling system for the ITER experimental fusion reactor. All maintenance inside the Vacuum Vessel (VV), such as maintenance of Blanket Modules, Divertors, and NBDL panels, needs to be performed remotely since the environment inside the VV will become highly radioactive once fusion operation begins. The NBDL Remote Handling (NBDL-RH) system is a subsystem of the Blanket Remote Handling System (BRHS) and is designed to be handled by the Vehicle Manipulator (VMNP) of BRHS. One of the key design challenges of this work is to develop a configuration that enables the NBDL-RH Tool to operate inside the Neutral Beam Duct independently from the VMNP, while also achieving operational efficiency. The NBDL-RH system was configured to consists of the NBDL-RH Tool, which functions within the Neutral Beam Duct; utility subsystem such as power supply and signal transmission; in-porting and out-porting subsystem for transporting the NBDL-RH Tool, in its various design configurations, into and out of the VV by means of cask transfers; and another supporting subsystem. To this end, the NBDL-RH Tool has been conceptually designed in a modular configuration incorporating a Tool Changer. This approach reduced the number of cask transfers by approximately one-third compared to a system without a Tool Changer. Furthermore, the modular configuration minimized the amount of manual reassembly work required in the Hot Cell Facility.
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.