Design, development and manufacture of the ITER Torus and cryostat cryopumps

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

Fusion Engineering and Design Pub Date : 2025-03-13 DOI:10.1016/j.fusengdes.2025.114939

Robert Pearce , J. Buckerfield , A. Iannetti , F. Chitu , A. Cobalt , S. Nasluzov , E. Quinn , F. Canadell , M. Dremel , L. Mora , G. Moner Pallas , J. Zeutschel

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Abstract

Eight large bespoke cryo-sorption pumps have been successfully manufactured for the pumping of ITER's divertor and cryostat. These pumps were a European in kind supply to the ITER project. They each have a nominal pumping speed of ∼100m³/s, weigh ∼8 tonnes each and will operate in synchronization to provide continuous high vacuum pumping of the vacuum vessel and cryostat in many different operational modes.

The cryopumps are some of the most complex components on the ITER tokamak, as vacuum/cryogenic components operating down to 4.5K and up to 470K, as precision mechanical components with moving parts on account of their integral 800mm all metal isolation valves and being nuclear components providing first confinement for tritium and nuclear shielding.

The time between the start of development of the pumps to the production pump deliveries is > 20 years involving many parties and dedicated efforts. Both a half size pump and a pre-production pump were built and tested as part of the development. Qualification and validation have been essential to ensure the pumps meet their performance requirements, nuclear safety functions and are built with a quality to function over tens of years.

This paper summarizes the experience gained and lessons learned from the design, validation and manufacturing process.

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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.