Commissioning of water detritiation and cryogenic distillation systems at TLK in view of ITER design

被引:34
作者
Cristescu, I.
Cristescu, Ioana R.
Doerr, L.
Glugla, M.
Hellriegel, G.
Michling, R.
Murdoch, D.
Schaefer, P.
Welte, S.
Wurster, W.
机构
[1] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
[2] EFDA, Close Support Unit, D-85748 Garching, Germany
关键词
tritium; water detritiation; hydrogen isotope separation; cryogenic distillation;
D O I
10.1016/j.fusengdes.2007.04.001
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 ITER Isotope Separation System (ISS) and Water Detritiation System (WDS) will be integrated in order to reduce potential chronic tritium releases from the ISS by routing the top (protium) product from the ISS into the Liquid Phase Catalytic Exchange (LPCE) column of WDS. This provides an additional barrier against ISS tritium releases and should mitigate the memory effects due to process parameter fluctuations in the ISS. To support the research activities needed to characterize the performances of various components for WDS and ISS processes in various working conditions and configurations as needed for ITER design, an experimental facility called TRENTA and representative of the ITER WDS and ISS protium separation column has been commissioned at Tritium Laboratory Karlsruhe (TLK). The TRENTA facility consists of Combined Electrolysis Catalytic Exchange (CECE) process, with an LPCE column of 8 m, in combination with a cryogenic distillation (CD) process. The processes description and the status of commissioning of TRENTA facility is presented. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:2126 / 2132
页数:7
相关论文
共 9 条
[1]  
ALEKSEEV IA, 1998, FUSION TECHNOL, V1, P959
[2]   Long term performances assessment of a water detritiation system components [J].
Cristescu, I ;
Cristescu, IR ;
Dörr, L ;
Glugla, M ;
Murdoch, D ;
Welte, S .
FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) :839-844
[3]   Trenta facility for trade-off studies between combined electrolysis catalytic exchange and cryogenic distillation processes [J].
Cristescu, I ;
Cristescu, IR ;
Dörr, L ;
Glugla, M ;
Hellriegel, G ;
Kveton, O ;
Murdoch, D ;
Schäfer, P ;
Welte, S .
FUSION SCIENCE AND TECHNOLOGY, 2005, 48 (01) :97-101
[4]   Investigation of separation performances of various isotope exchange catalysts for the deuterium-hydrogen system [J].
Cristescu, I ;
Cristescu, IR ;
Tamm, U ;
Penzhorn, RD ;
Caldwell-Nichols, CJ .
FUSION SCIENCE AND TECHNOLOGY, 2002, 41 (03) :1087-1091
[5]   Iter dynamic tritium inventory modeling code [J].
Cristescu, IR ;
Dörr, L ;
Busigin, A ;
Murdoch, D .
FUSION SCIENCE AND TECHNOLOGY, 2005, 48 (01) :343-348
[6]  
*ITER, 32E WBS ITER
[7]   Overview of Canadian activities in tritium [J].
Miller, JM .
FUSION SCIENCE AND TECHNOLOGY, 2002, 41 (03) :314-318
[8]   The prediction of tritium level reduction of Wolsong NPPs by heavy water detritiation with WTRF [J].
Song, KM ;
Lee, SJ ;
Lee, SK ;
Sohn, SH ;
Eum, HM ;
Kim, CS .
FUSION SCIENCE AND TECHNOLOGY, 2005, 48 (01) :290-293
[9]  
ITERD2234RH