Potential and limits of water cooled divertor concepts based on monoblock design as possible candidates for a DEMO reactor

Potential and limits of water cooled divertor concepts based on monoblock design as possible candidates for a DEMO reactor
复制标题

DOI:
10.1016/j.fusengdes.2013.05.114
复制
发表时间:
2013-10-01
影响因子:
1.7
通讯作者:
Ridolfini, Vincenzo Pericoli
Ridolfini, Vincenzo Pericoli
中科院分区:
工程技术3区
文献类型:
--
作者:
Li-Puma, Antonella;Richou, Marianne;Ridolfini, Vincenzo Pericoli

文献摘要

被引文献

相似文献

在本文中,已经审查了基于先前研究中确定为融合发电厂的候选的钨单块设计的水冷分流概念,以评估其潜力和限制,以作为短期到中期的演示概念可交付的候选者(“保守基线”设计”)。考虑到有关反应堆参数,材料属性和制造技术的当前事实信息,将重新审视导致其选择的基本原理和技术发展假设。为此,确定了影响分离型分离设计的主要参数并讨论了其相关性。审查了有关材料和相关制造技术的艺术知识。辐照后特别注意材料特性的变化;现象阈值(如果有)和可能的操作范围(就温度和损伤剂量而言)。过去提出的各种拟议的散热器/结构和牺牲层材料的适用性得到了重新评估(例如,关于减少峰热通量和/或中子辐射损害的可能性)。结果,突出显示了各种提出的概念的潜在和限制,它们可以在其中(如果有)进行操作并提出可能的改进。报告了研发活动。这项工作是在EFDA PPPT工作计划活动的框架内进行的。 (c)2013 Elsevier B.V.保留所有权利。
In this paper water-cooled divertor concepts based on tungsten monoblock design identified in previous studies as candidate for fusion power plant have been reviewed to assess their potential and limits as possible candidates for a DEMO concept deliverable in a short to medium term ("conservative baseline design"). The rationale and technology development assumptions that have led to their selection are revisited taking into account present factual information on reactor parameters, materials properties and manufacturing technologies.For that purpose, main parameters impacting the divertor design are identified and their relevance discussed. The state of the art knowledge on materials and relevant manufacturing techniques is reviewed. Particular attention is paid to material properties change after irradiation; phenomenon thresholds (if any) and possible operating ranges are identified (in terms of temperature and damage dose). The suitability of various proposed heat sink/structural and sacrificial layer materials, as proposed in the past, are re-assessed (e.g. with regard to the possibility of reducing peak heat flux and/or neutron radiation damages). As a result, potential and limits of various proposed concepts are highlighted, ranges in which they could operate (if any) defined and possible improvements are proposed.Identified missing point in materials database and/or manufacturing techniques knowledge that should be uppermost investigated in future R&D activities are reported.This work has been carried out in the frame of EFDA PPPT Work Programme activities. (C) 2013 Elsevier B.V. All rights reserved.