Measurement and Monitoring of Tritium and Other Critical Issues in Lead Lithium Ceramic Breeder (LLCB)
作者： V. K. Tangri , Sadhana Mohan , A. Narayanan , K. K. Narayan
DOI: 10.13182/FST08-A1776
关键词: Blanket 、 Solvent extraction 、 Ceramic 、 Tritium 、 Nuclear engineering 、 Environmental science 、 Monitoring system 、 High surface area 、 Helium
摘要: A new Indian concept involving a lead lithium ceramic breeder is being explored. LLCB based tritium blanket modules require extraction from lead-lithium as well helium purge gas. This paper addresses the of efficiency enhancement using high surface area, low-pressure drop structured gas liquid contactors for lithium. Conceptual flow schemes both loops are discussed and critical issues highlighted. Tritium monitoring systems (TMS) measurement also dealt. fast responding monitor has been developed in situ water or form. It tested effluents. (authors)
osti.gov
ans.org 参考文章(9)
Carlo Malara, Tritium Extraction from Pb-17Li by Bubble Columns Fusion Technology. ,vol. 28, pp. 693- 699 ,(1995) , 10.13182/FST95-A30485
G. Pierini, R. Baratti, A.M. Polcaro, P.F. Ricci, A. Viola, Mass Transfer Operational Units Applied to the Liquid Breeding Material of Fusion Reactors for Tritium Recovery Fusion Technology. ,vol. 8, pp. 2121- 2126 ,(1985) , 10.13182/FST85-A24597
L.V. Boccaccini, J.-F. Salavy, R. Lässer, A. Li Puma, R. Meyder, H. Neuberger, Y. Poitevin, G. Rampal, The European test blanket module systems: Design and integration in ITER Fusion Engineering and Design. ,vol. 81, pp. 407- 414 ,(2006) , 10.1016/J.FUSENGDES.2005.09.008
L. Giancarli, V. Chuyanov, M. Abdou, M. Akiba, B.G. Hong, R. Lässer, C. Pan, Y. Strebkov, Breeding Blanket Modules testing in ITER: An international program on the way to DEMO Fusion Engineering and Design. ,vol. 81, pp. 393- 405 ,(2006) , 10.1016/J.FUSENGDES.2005.08.096
Takayuki Terai, Shin'ichi Nagai, Toshiaki Yoneaka, Yoichi Takahashi, Mass transfer coefficient of tritium from molten lithium-lead alloy (Li17Pb83) to environmental gas under neutron irradiation Fusion Engineering and Design. ,vol. 17, pp. 237- 241 ,(1991) , 10.1016/0920-3796(91)90064-W
A. Ying, M. Abdou, C. Wong, S. Malang, N. Morley, M. Sawan, B. Merrill, D.K. Sze, R. Kurtz, S. Willms, M. Ulrickson, S. Zinkle, An overview of US ITER test blanket module program Fusion Engineering and Design. ,vol. 81, pp. 433- 441 ,(2006) , 10.1016/J.FUSENGDES.2005.06.379
K.M. Feng, C.H. Pan, G.S. Zhang, D.L. Luo, Z.W. Zhou, Y.W. Yang, X.Y. Wang, G. Hu, T. Yuan, Z. Chen, H.Y. Wang, C.A. Chen, Z.X. Li, Z. Zhao, Z.Q. Li, Preliminary design for a China ITER test blanket module Fusion Engineering and Design. ,vol. 81, pp. 1219- 1224 ,(2006) , 10.1016/J.FUSENGDES.2005.09.052
Mikio Enoeda, Masato Akiba, Satoru Tanaka, Akihiko Shimizu, Akira Hasegawa, Satoshi Konishi, Akihiko Kimura, Akira Kohyama, Akio Sagara, Takeo Muroga, Overview of design and R&D of test blankets in Japan Fusion Engineering and Design. ,vol. 81, pp. 415- 424 ,(2006) , 10.1016/J.FUSENGDES.2005.08.097
D. K. Sze, Counter current extraction system for tritium recovery from 17Li-83Pb Fusion Science and Technology. ,vol. 8, pp. 887- 890 ,(1985) , 10.13182/FST85-A40145