Materials-engineering challenges for the fusion core and lifetime components of the fusion nuclear science facility

被引：19

作者：

Rowcliffe, A. F. ^{[1
]}

Kessel, C. E. ^{[2
]}

Katoh, Y. ^{[1
]}

Garrison, L. M. ^{[1
]}

Tan, L. ^{[1
]}

Yamamoto, Y. ^{[1
]}

Wiffen, F. W. ^{[1
]}

机构：

[1] Oak Ridge Natl Lab, Oak Ridge, TN USA

[2] Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA

来源：

NUCLEAR MATERIALS AND ENERGY | 2018年 / 16卷

关键词：

RESEARCH-AND-DEVELOPMENT; CORROSION BEHAVIOR; FLOWING PB-15.7LI; POWER-PLANT; BLANKET; DESIGN; DEMO; REACTOR; INTEGRATION; EUROFER;

D O I：

10.1016/j.nme.2018.05.025

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

From the perspective of materials research and development (R&D) for the fusion core and near-core lifetime components of deuterium-tritium fusion power systems, the Fusion Neutron Science Facility (FNSF) concept plays a very important function by generating the complete fusion in-service environment and providing a platform for materials component-level testing. The FNSF provides the critical link between the ITER-era and the electricity-producing facilities, DEMO and the commercial power plant. The main features of the FNSF are described and the rationale presented for the selection of structural materials to meet the challenges of the power core components and also for the system lifetime components. The calculated radiation damage parameters and potential operating temperatures requirements for each of the operational phases are presented ranging from nuclear break-in up to DEMO relevant conditions. The interdependence of the FNSF and fusion nuclear materials research are discussed, and examples of near-term materials R&D activities are outlined which could address several current FNSF-related design issues.

引用

页码：82 / 87

页数：6

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[31] On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of ∼8Cr tempered martensitic steels:: Compilation and analysis of existing data [J].