G. Aiello , C. Bachmann , J. Henry , G. Pintsuk , M. Rieth , D. Terentyev
{"title":"Screening of suitable and testable structural materials for a volumetric neutron source","authors":"G. Aiello , C. Bachmann , J. Henry , G. Pintsuk , M. Rieth , D. Terentyev","doi":"10.1016/j.fusengdes.2025.115460","DOIUrl":null,"url":null,"abstract":"<div><div>The construction of a dedicated Volumetric Neutron Source (VNS) has recently been proposed to de-risk the path towards the licensing of EU DEMO and to bring the required technologies, in particular the Breeding Blanket, to the required Technology Readiness Level. The programmatic goals, the operating conditions and the associated requirements of this machine are different from the fusion power machines (ITER, DEMO) considered until now in the European Research Roadmap. A critical analysis and a possible reassessment of the material choices for the Vacuum Vessel (VV) and In-Vessel Components established for ITER and DEMO is therefore a required preparatory step. Starting from the materials used in the ITER VV and Shielding Blanket, their limits w.r.t. maximum allowable dose are discussed and possible alternatives to maximize the lifetime of the facility are proposed. The materials currently considered for the EU-DEMO Breeding Blanket are recalled and an overview of their present development status is provided. Materials and joining issues for Divertor targets are also discussed. The gaps in materials properties and the needs for additional characterizations are identified. The purpose of this paper is to provide options and information for designers, exploring the operational space of the VNS, the final selection of materials depending on the strategic goals and design choices that will be set for the facility.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115460"},"PeriodicalIF":2.0000,"publicationDate":"2025-09-25","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/S0920379625006568","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
The construction of a dedicated Volumetric Neutron Source (VNS) has recently been proposed to de-risk the path towards the licensing of EU DEMO and to bring the required technologies, in particular the Breeding Blanket, to the required Technology Readiness Level. The programmatic goals, the operating conditions and the associated requirements of this machine are different from the fusion power machines (ITER, DEMO) considered until now in the European Research Roadmap. A critical analysis and a possible reassessment of the material choices for the Vacuum Vessel (VV) and In-Vessel Components established for ITER and DEMO is therefore a required preparatory step. Starting from the materials used in the ITER VV and Shielding Blanket, their limits w.r.t. maximum allowable dose are discussed and possible alternatives to maximize the lifetime of the facility are proposed. The materials currently considered for the EU-DEMO Breeding Blanket are recalled and an overview of their present development status is provided. Materials and joining issues for Divertor targets are also discussed. The gaps in materials properties and the needs for additional characterizations are identified. The purpose of this paper is to provide options and information for designers, exploring the operational space of the VNS, the final selection of materials depending on the strategic goals and design choices that will be set for the 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.