Conceptual design on interface between ITER and tritium extraction system of Chinese helium-cooled solid breeder test blanket module

被引：5

作者：

Zhang Long ^{[1
]}

Luo Tianyong ^{[1
]}

Feng Kaiming ^{[1
]}

机构：

[1] SW Inst Phys, Fus Reactor & Nucl Mat Div, Chengdu 610041, Sichuan, Peoples R China

来源：

FUSION ENGINEERING AND DESIGN | 2010年 / 85卷 / 10-12期

关键词：

ITER; TBM; Tritium extraction; CRYOGENIC MOLECULAR-SIEVE; HYDROGEN ISOTOPES; PURGE GAS; ADSORPTION; RECOVERY; BED;

D O I：

10.1016/j.fusengdes.2010.08.041

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：

Tritium extraction system is essential for CN HCSB TBM for safety and technical reasons. Based on the assessments of system functions, integration issues and safety considerations, two main modifications of the system from previous design (Feng et al., 2007 [1]; Chen et al., 2008 [2]) are adopted: a) the TES has been split to 2 parts with one in port cell and another in tritium building. Q(2)O in the purge gas is reduced to Q(2) in a hot metal bed located in port cell; Q(2) is separated from the stream by a pair of cryogenic molecular sieve beds and a Pd/Ag diffuser located in tritium building. b) isotope separation process has been excluded. TES components sizes are estimated and space allocations are estimated. Required services and where and when they are needed are preliminary defined. Fluids delivered towards ITER tritium system are analyzed. (C) 2010 Elsevier B.V. All rights reserved.

引用

页码：2213 / 2216

页数：4

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