Development and qualification of functional materials for the European HCPB TBM

被引：32

作者：

Zmitko, M. ^{[1
]}

Vladimirov, P. ^{[2
]}

Knitter, R. ^{[2
]}

Kolb, M. ^{[2
]}

Leys, O. ^{[2
]}

Heuser, J. ^{[2
]}

Schneider, H. -C. ^{[2
]}

Rolli, R. ^{[2
]}

Chakin, V. ^{[2
]}

Pupeschi, S. ^{[2
]}

Magielsen, L. ^{[3
]}

Fedorov, A. ^{[3
]}

Poitevin, Y. ^{[1
]}

机构：

[1] Fus Energy F4E, Josep Pla 2, Barcelona, Spain

[2] KIT, Postfach 3640, Karlsruhe, Germany

[3] NRG Nucl Res & Consultancy Grp, POB 25, NL-1755 ZG Petten, Netherlands

来源：

FUSION ENGINEERING AND DESIGN | 2018年 / 136卷

关键词：

ITER; Test blanket modules (TBM); Ceramic breeder; Beryllium multiplier; Post-irradiation examination (PIE); BERYLLIUM PEBBLES; TRITIUM; RELEASE; HELIUM; IRRADIATION; DESIGN;

D O I：

10.1016/j.fusengdes.2018.05.014

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 paper reviews the current status of development and qualification of the HCPB TBM's functional materials, namely, Li-ceramic breeder and Be multiplier materials. The main functional and performance requirements for both functional materials are overviewed. The main results and outcomes of the post-irradiation examinations (PIE) of Li-ceramic breeder and Be/beryllides materials irradiated in HIDOBE and HICU irradiation campaigns are presented aiming at determination of the materials' performance, properties and characteristics under neutron irradiation, like e.g. morphology and microstructure, tritium retention/release characteristics, mechanical properties. Fabrication of the advanced ceramic breeder material, containing lithium orthosilicate with addition of lithium metatitanate phase in order to improve its mechanical properties, is described. Results of characterization of this advanced ceramic breeder in terms of mechanical properties, porosity, morphology and effective thermal conductivity of a pebble bed are overviewed. In addition, results of characterization of the reference 1 mm Be pebbles produced by Rotation Electrode Process are presented in terms of their microstructure, tritium release characteristics and interaction with air and steam. A necessity to realize in the future a new irradiation experiment for the functional materials, LIBERTI experiment, is discussed in the conclusions.

引用

页码：1376 / 1385

页数：10

共 24 条

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