Liquid surfaces for fusion plasma facing components-A critical review. Part I: Physics and PSI

被引：108

作者：

Nygren, R. E. ^{[1
]}

Tabares, F. L. ^{[2
]}

机构：

[1] Sandia Natl Labs, POB 5800, Albuquerque, NM 87185 USA

[2] Assoc CIEMAT, Madrid, Spain

来源：

NUCLEAR MATERIALS AND ENERGY | 2016年 / 9卷

关键词：

Liquid surface; Plasma facing components; Plasma facing materials; Divertor; First wall; Fusion technology; CAPILLARY-PORE SYSTEMS; HIGH-HEAT-FLUX; LITHIUM LIMITER; 1ST EXPERIMENTS; PERFORMANCE; DIVERTOR; TOKAMAK; EAST; RETENTION; COATINGS;

D O I：

10.1016/j.nme.2016.08.008

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：

This review of the potential of robust plasma facing components (PFCs) with liquid surfaces for applications in future D/T fusion device summarizes the critical issues for liquid surfaces and research being done worldwide in confinement facilities, and supporting R&D in plasma surface interactions. In the paper are a set of questions and related criteria by which we will judge the progress and readiness of liquid surface PFCs. Part-II (separate paper) will cover R&D on the technology-oriented aspects of liquid surfaces including the liquid surfaces as integrated first walls in tritium breeding blankets, tritium retention and recovery, and safety. (C) 2016 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

引用

页码：6 / 21

页数：16

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