Preliminary design of the remote handling system for the ITER vacuum vessel pressure suppression system

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-09 DOI:10.1016/j.fusengdes.2025.114994

Taku Yokoyama , Chang-Hwan Choi , Shanshuang Shi , Gong Zheng , David Hamilton , Jinwook Kim , Jim Palmer , Garin Schoonhoven , Paul Talbot , Francesco Becchi

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引用次数: 0

Abstract

The Vacuum Vessel Pressure Suppression System Remote Handling Equipment (VVPSS RHE) is being developed for remote maintenance of VVPSS components, including the Rupture Disc Assembly (RDA), Bleed Line Valve Assembly (BLVA), Support Trolley and relief lines within the Neutral Beam (NB) cell. It works in conjunction with the Neutral Beam Remote Handling System (NBRHS), including the Monorail Crane System (MCS) and Beam Line Transporter (BLT) manipulator. The main functions of the VVPSS RHE are to disconnect and reconnect bolted flanges, limit the spread of contamination and clean relief lines to reduce internal contamination and radiation levels in the NB cell. This paper describes the remote handling (RH) interfaces and the preliminary design of the VVPSS RHE, which demonstrate the feasibility of maintenance operations within the constrained NB cell environment and the capability of the NBRHS.

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ITER真空容器压力抑制系统远程操作系统初步设计

正在开发的真空容器压力抑制系统远程处理设备（VVPSS RHE）用于远程维护 VVPSS 组件，包括爆破片组件 (RDA)、放气阀组件 (BLVA)、支撑小车和中性梁 (NB) 单元内的泄压管。它与中性梁远程处理系统 (NBRHS) 配合使用，包括单轨起重机系统 (MCS) 和梁线运输机 (BLT) 机械手。VVPSS RHE 的主要功能是断开和重新连接螺栓法兰、限制污染扩散和清洁泄压管，以降低 NB 单元的内部污染和辐射水平。本文介绍了远程处理（RH）接口和 VVPSS RHE 的初步设计，证明了在受限制的 NB 单元环境中进行维护操作的可行性以及 NBRHS 的能力。

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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.