Abstract
Systems to Recover Tritium (T) from Fusion Liquid Blankets of LiPb (Li 17Pb18) and Flibe (Li2BeF4 under safety conditions are discussed based on available data of T transport properties. We recently performed experiments on hydrogen isotopes permeating through LiPb in Kyushu University and introduced them in the present paper. Solubilities, diffusivities and permeabilities of H and D through Li 17Pb83 are determined by means of a transient permeation method. Their isotope effects between H and D in the Li-Pb eutectic alloy are found to be independent of D/H atomic ratio and a function of only temperature. Tritium recovery apparatuses of a liquid-gas counter-current flowing bed or a T permeation window are designed in the liquid blanket system composed of the primary coolant of Flibe or LiPb and the secondary coolant of He or water. Simultaneous transfer of heat and T needs new configuration in order to satisfy the necessary conditions of low T leak and high heat transfer, which make it possible to operate the blanket effectively and safely. Tritium permeation rates through the primary LiPb or Flibe breeder and secondary water or He coolant loops are estimated, which is the most important factor to operate the blanket safely.
| Original language | English |
|---|---|
| Pages (from-to) | 58-63 |
| Number of pages | 6 |
| Journal | Fusion Science and Technology |
| Volume | 61 |
| Issue number | 1 T |
| DOIs | |
| Publication status | Published - Jan 1 2012 |
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All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Cite this
Tritium recovery from liquid blanket systems for fusion reactor. / Fukada, Satoshi; Edao, Y.; Katekari, K.; Okitsu, H.; Hatachi, Y.; Okada, M.; Tamari, K.
In: Fusion Science and Technology, Vol. 61, No. 1 T, 01.01.2012, p. 58-63.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Tritium recovery from liquid blanket systems for fusion reactor
AU - Fukada, Satoshi
AU - Edao, Y.
AU - Katekari, K.
AU - Okitsu, H.
AU - Hatachi, Y.
AU - Okada, M.
AU - Tamari, K.
PY - 2012/1/1
Y1 - 2012/1/1
N2 - Systems to Recover Tritium (T) from Fusion Liquid Blankets of LiPb (Li 17Pb18) and Flibe (Li2BeF4 under safety conditions are discussed based on available data of T transport properties. We recently performed experiments on hydrogen isotopes permeating through LiPb in Kyushu University and introduced them in the present paper. Solubilities, diffusivities and permeabilities of H and D through Li 17Pb83 are determined by means of a transient permeation method. Their isotope effects between H and D in the Li-Pb eutectic alloy are found to be independent of D/H atomic ratio and a function of only temperature. Tritium recovery apparatuses of a liquid-gas counter-current flowing bed or a T permeation window are designed in the liquid blanket system composed of the primary coolant of Flibe or LiPb and the secondary coolant of He or water. Simultaneous transfer of heat and T needs new configuration in order to satisfy the necessary conditions of low T leak and high heat transfer, which make it possible to operate the blanket effectively and safely. Tritium permeation rates through the primary LiPb or Flibe breeder and secondary water or He coolant loops are estimated, which is the most important factor to operate the blanket safely.
AB - Systems to Recover Tritium (T) from Fusion Liquid Blankets of LiPb (Li 17Pb18) and Flibe (Li2BeF4 under safety conditions are discussed based on available data of T transport properties. We recently performed experiments on hydrogen isotopes permeating through LiPb in Kyushu University and introduced them in the present paper. Solubilities, diffusivities and permeabilities of H and D through Li 17Pb83 are determined by means of a transient permeation method. Their isotope effects between H and D in the Li-Pb eutectic alloy are found to be independent of D/H atomic ratio and a function of only temperature. Tritium recovery apparatuses of a liquid-gas counter-current flowing bed or a T permeation window are designed in the liquid blanket system composed of the primary coolant of Flibe or LiPb and the secondary coolant of He or water. Simultaneous transfer of heat and T needs new configuration in order to satisfy the necessary conditions of low T leak and high heat transfer, which make it possible to operate the blanket effectively and safely. Tritium permeation rates through the primary LiPb or Flibe breeder and secondary water or He coolant loops are estimated, which is the most important factor to operate the blanket safely.
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UR - http://www.scopus.com/inward/citedby.url?scp=84857584249&partnerID=8YFLogxK
U2 - 10.13182/FST12-A13397
DO - 10.13182/FST12-A13397
M3 - Article
AN - SCOPUS:84857584249
VL - 61
SP - 58
EP - 63
JO - Fusion Science and Technology
JF - Fusion Science and Technology
SN - 1536-1055
IS - 1 T
ER -