Clarification of Tritium Behavior in Pb-Li Blanket System

被引:14
作者
Fukada, S. [1 ]
Terai, T. [2 ]
Konishi, S. [3 ]
Katayama, K. [1 ]
Chikada, T. [2 ]
Edao, Y. [1 ,4 ]
Muroga, T. [5 ]
Shimada, M. [6 ]
Merrill, B. [6 ]
Sze, D. K. [7 ]
机构
[1] Kyushu Univ, Interdisciplinary Grad Sch Engn Sci, Dept Adv Energy Engn Sci, Fukuoka 8128581, Japan
[2] Univ Tokyo, Inst Engn Innovat, Dept Nucl Engn & Management, Tokyo 1138656, Japan
[3] Kyoto Univ, Adv Atom Energy Res Sect, Inst Adv Energy, Kyoto 6110011, Japan
[4] Japan Atom Energy Agcy, Ibaraki 3191195, Japan
[5] Natl Inst Nat Sci, Natl Inst Fus Sci, Toki, Gifu 5095292, Japan
[6] Idaho Natl Lab, Idaho Falls, ID 83415 USA
[7] Univ Calif San Diego, La Jolla, CA 92093 USA
基金
日本学术振兴会;
关键词
lead-lithium; liquid blanket; tritium; isotope effects; solubility; diffusivity; permeability; ceramic coating; HYDROGEN ISOTOPES; PHASE-DIAGRAM; LEAD; LITHIUM; DIFFUSION; RECOVERY; PB-17LI;
D O I
10.2320/matertrans.MG201203
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In order to clarify the tritium behavior in Pb-Li blanket system, the solubility of hydrogen isotopes in the Pb-Li eutectic alloy was experimentally investigated. The effects of (i) Li preferential evaporation from Pb-Li, (ii) thermal convection in a quartz-glass reaction tube and (iii) difference in crucible materials between Al2O3 and W on the solubilities were discussed. Another important issue of the Pb-Li blanket system is to develop a new ceramic coating to decrease tritium permeation rate. Tritium permeation test was performed for Er2O3 coating on F82H. The permeation reduction factor achieved here was higher than 10(3). Precise experiments were carried out to determine the solubility, diffusivity and permeability of hydrogen isotopes in Pb-Li eutectic alloy by means of a transient permeation method. The isotope effects in solubility and diffusivity between H and D were clarified. No isotope effect in solubility was observed between H and D, and the H diffusivity was 1.4 times larger than the D one. The ratio was near to a value predicted from the classical theory. Experiment using tritium is designed under the collaboration work with INL.
引用
收藏
页码:425 / 429
页数:5
相关论文
共 22 条
[1]  
Alock C. B., 1994, J PHYS CHEM REF DATA, V23, P385
[2]   A CHEMICAL THEORY ANALYSIS OF THE SOLUTION THERMODYNAMICS OF OXYGEN, NITROGEN AND HYDROGEN IN LEAD-RICH LI-PB MIXTURES [J].
BUXBAUM, RE .
JOURNAL OF THE LESS-COMMON METALS, 1984, 97 (FEB) :27-38
[3]   Neutronics analyses of tritium breeding blanket performance in a spherical torus based volumetric neutron source [J].
Cerbone, RJ ;
Cheng, ET ;
Peng, YKM .
FUSION TECHNOLOGY, 1998, 34 (03) :779-783
[4]   Surface behaviour in deuterium permeation through erbium oxide coatings [J].
Chikada, T. ;
Suzuki, A. ;
Adelhelm, C. ;
Terai, T. ;
Muroga, T. .
NUCLEAR FUSION, 2011, 51 (06)
[5]   MODELING OF TRITIUM PERMEATION THROUGH ERBIUM OXIDE COATINGS [J].
Chikada, Takumi ;
Suzuki, Akihiro ;
Maier, Hans ;
Terai, Takayuki ;
Muroga, Takeo .
FUSION SCIENCE AND TECHNOLOGY, 2011, 60 (01) :389-393
[6]   Microstructure change and deuterium permeation behavior of erbium oxide coating [J].
Chikada, Takumi ;
Suzuki, Akihiro ;
Kobayashi, Tomohiro ;
Maier, Hans ;
Terai, Takayuki ;
Muroga, Takeo .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :1241-1244
[7]   PERMEATION OF TWO-COMPONENT HYDROGEN ISOTOPES IN LITHIUM-LEAD EUTECTIC ALLOY [J].
Edao, Y. ;
Okitsu, H. ;
Noguchi, H. ;
Fukada, S. .
FUSION SCIENCE AND TECHNOLOGY, 2011, 60 (03) :1163-1166
[8]   Experiments of hydrogen isotope permeation, diffusion and dissolution in Li-Pb [J].
Edao, Yuki ;
Noguchi, Hidetaka ;
Fukada, Satoshi .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :723-726
[9]   EVAPORATION OF LEAD AND LITHIUM FROM MOLTEN PB-17LI - TRANSPORT OF AEROSOLS [J].
FEUERSTEIN, H ;
GRABNER, H ;
OSCHINSKI, J ;
HORN, S ;
BENDER, S .
FUSION ENGINEERING AND DESIGN, 1991, 17 :203-207
[10]   Tritium recovery system for Li-Pb loop of inertial fusion reactor [J].
Fukada, S. ;
Edao, Y. ;
Yamaguti, S. ;
Norimatsu, T. .
FUSION ENGINEERING AND DESIGN, 2008, 83 (5-6) :747-751