A risk analysis for Helium Cooling System (HCS) of HCCP-TBS

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

Fusion Engineering and Design Pub Date : 2025-03-06 DOI:10.1016/j.fusengdes.2025.114921

Daniel Moya Alonso , Youngmin Lee , Enric Bargalló Font , Chang Shuk Kim , Myungho Kim , Changwook Shin , Seok-Kwon Son , Mu-Young Ahn , Martín Gorriarán Vicario , Javier Leboreiro Iriarte

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引用次数: 0

Abstract

Climate change is a reality. Every day, the effects of it are visible and one of the main challenges is to achieve carbon neutrality by 2050. With this goal, one increasing technology in clean energy generation is nuclear fusion. Nuclear fusion needs unique working conditions, such as: extremely elevated temperatures, strong electromagnetic fields, and ultra-high vacuum conditions. But another challenging milestone should be taken into account: breeding tritium. Tritium quantity is naturally scarce on Earth and has to be generated, which is costly and currently very limited. One of the missions for the later stages of ITER operation is to demonstrate the feasibility of producing tritium from lithium within the vacuum vessel, making breeding blankets a key component of ITER.

Given its relevance, there are several proposals to breed tritium, from using helium or water as a coolant, or liquid types like lithium-lead (LiPb) alloy or solid types such as lithiated ceramic pebbles as breeder. One of the proposals being currently developed, is the Helium Cooled Ceramic Pebble (HCCP), where lithiated ceramic pebbles are used as breeder and helium, as coolant. HCCP is designed to test tritium breeding, recovery, and withstand reactor loads. A key function is heating removal, with the Helium Cooling System (HCS) essential for ITER's safety and availability.

This paper describes the Reliability, Availability, Maintainability and Inspectability (RAMI) analysis and preliminary risk assessment (HAZOP) performed, together with the proposed design, operation and maintenance suggestions needed to achieve the mail goal: a reliable and safe operation for HCCP-HCS.

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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.