Conceptual design of Tritium Extraction System for the European HCPB Test Blanket Module

被引：36

作者：

Ciampichetti, A. ^{[1
]}

Nitti, F. S. ^{[1
]}

Aiello, A. ^{[1
]}

Ricapito, I. ^{[2
]}

Liger, K. ^{[3
]}

Demange, D. ^{[4
]}

Sedano, L. ^{[5
]}

Moreno, C. ^{[5
]}

Succi, M. ^{[6
]}

机构：

[1] ENEA CR Brasimone, I-40032 Camugnano, Bo, Italy

[2] Fus Energy, Barcelona 08019, Spain

[3] CEA, DEN, DTN STPA LIPC, F-13108 St Paul Les Durance, France

[4] Karlsruhe Inst Technol, ITEP TLK, D-76021 Karlsruhe, Germany

[5] EURATOM CIEMAT Assoc, Madrid 28040, Spain

[6] SAES Getters Spa, I-20020 Lainate, Mi, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2012年 / 87卷 / 5-6期

关键词：

ITER; Ceramic breeding blanket; Tritium extraction; Tritium removal;

D O I：

10.1016/j.fusengdes.2012.01.047

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：

The HCPB (Helium Cooled Pebble Bed) Test Blanket Module (TBM), developed in EU to be tested in ITER, adopts a ceramic containing lithium as breeder material, beryllium as neutron multiplier and helium at 80 bar as primary coolant. In HCPB-TBM the main function of Tritium Extraction System (TES) is to extract tritium from the breeder by gas purging, to remove it from the purge gas and to route it to the ITER Tritium Plant for the final tritium processing. In this paper, starting from a revision of the so far reference process considered for HCPB-TES and considering a new modeling activity aimed to evaluate tritium concentration in purge gas, an updated conceptual design of TES is reported. (C) 2012 Elsevier B.V. All rights reserved.

引用

页码：620 / 624

页数：5

共 9 条

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