Cernavoda tritium removal facility: A key tritium supplier for future fusion facilities

被引:6
|
作者
Stefan, Liviu [1 ]
Trantea, Nicolae [2 ]
Bornea, Anisia [1 ]
Zamfirache, Marius [1 ]
Bidica, Nicolae [1 ]
Stefan, Iuliana [1 ]
机构
[1] ICSI, Str Uzinei 4, Ramnicu Valcea, Romania
[2] CNE, Str Medgidia 1, Cernavoda, Romania
关键词
Tritium; Detritiation; TRF; Fusion;
D O I
10.1016/j.fusengdes.2019.02.116
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
National R&D for Cryogenics and Isotopes Separation (ICSI) completed the conceptual design of the Cernavoda Tritium Removal Facility (CTRF) in 2015. CTRF is located at CNE1 Cernavoda and is sized to process 40 kg/h heavy water from 2 CANDU reactors, with a detritiation factor of 100, over 40 years design life. CTRF removes tritium using liquid phase catalytic exchange (LPCE) paired with cryogenic distillation (CD). The design of CTRF uses expertise from ICSI (Pilot Plant for Tritium and Deuterium Separation) and from Canada (Kinectrics), together with experience from Wolsung TRF project, research tritium laboratories and industry. The CTRF design uses the most advanced TRF technology, including recent safety requirements for a tritium industrial facility as specified by the Romanian Regulator. Construction of CTRF is planned to start in 2020 and the detritiation of heavy water from first reactor is scheduled to begin in 2026. After this date tritium stored will become available to be used for fusion research and industrial facilities. First phase of detritiation process is to reduce the moderator tritium content from 65 Ci/kg to 10 Ci/kg, second phase to maintain the tritium concentration up to 10 Ci/kg and third phase to use CTRF to reduce tritium content as low as possible before decommissioning of the site. This paper will present the technologies used, provide a prediction of tritium production, and considerations for possible use of CTRF for supplying He-3, as a by-product of the detritiation process.
引用
收藏
页码:1505 / 1509
页数:5
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