Latest design of liquid lithium target in IFMIF

Nakamura, Hiroo; Agostini, P.; Ara, K.; Cevolani, S.; Chida, T.; Ciotti, Marco; Fukada, Satoshi; Furuya, Kazuo; Garin, P.; Gessii, A.; Guisti, D.; Heinzel, V.; Horiike, Hiroshi; Ida, Masato; Jitsukawa, S.; Kanemura, Takuji; Kondo, Hiroo; Kukita, Yutaka; Lösser, R.; Matsui, H.; Miccichè, G.; Miyashita, Makoto; Muroga, T.; Riccardi, B.; Simakov, S.P.; Stieglitz, Robert; Sugimoto, M.; Suzuki, Akihiro; Tanaka, S.; Terai, Takayuki; Yagi, Juro; Yoshida, E.; Wakai, Eiichi

doi:10.1016/j.fusengdes.2008.06.014

Cited by 23 publications

(18 citation statements)

References 13 publications

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“…• C. Guiding the lithium flow with a speed of 15 m/s along the concave back plate is required to increase the pressure in the lithium flow by centrifugal force, to avoid boiling by the heat input about 1 GW of the deuteron beams [7] and to remove heat by the lithium flow circulation under the lithium purification controls by N hot trap, H hot trap, and cold trap [8][9][10].…”

Section: Introductionmentioning

confidence: 99%

“…On the other hand, the solubility of nitrogen and hydrogen in lithium is large even at around the melting point of lithium; therefore, both elements should be removed from the liquid lithium chemically with other traps, which are so called hot traps. The related recent activities of lithium purification studies were reported in the references [8][9][10][11][12][13][14][15][16][17][18], and the content of the lithium test facility of IFMIF have been reported in the references [8,9,[19][20][21][22][23][24][25][26][27].…”

Section: Introductionmentioning

confidence: 99%

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Nitrogen Hot Trap Design and Manufactures for Lithium Test Loop in IFMIF/EVEDA Project

Wakai

Watanabe

Ito

et al. 2016

Plasma and Fusion Research

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The lithium target facility of IFMIF (International Fusion Materials Irradiation Facility) consists of target assembly, lithium main loop, lithium purification loops, the diagnostic systems, and remote handling system. Major impurities in the lithium loop are proton, deuterium, tritium, 7-Be, activated corrosion products and the other species (C, N, O). It is very important to remove nitrogen content in lithium loop during operation, in order to avoid the corrosion/erosion of the nozzle of lithium target for the stable lithium flow on the target assembly. Nitrogen in the lithium can be removed by N hot trap using Fe-5%Ti alloy at temperatures from 400 to 600• C. In this study, the specification and the detailed design were evaluated, and the component of N hot trap system was fabricated.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Nitrogen Hot Trap Design and Manufactures for Lithium Test Loop in IFMIF/EVEDA Project

Wakai

Watanabe

Ito

et al. 2016

Plasma and Fusion Research

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“…Quest for more intense neutron source resulted in a combination of Li target and intense deutron or proton beams to avoid destruction of target itself by own generated neutrons. The facility of the internaitional fusion material irradiation facility (IFMIF) is now under development to generate 10 16-17 neutrons per second at 14MeV comtinuously [1,2]. In the early phase of the development, the solid target was abandoned, since the solid target sufferes strongest irradiation damage from own neutrons, and results in destruction before full irradiation on the test specimen is completed.…”

Section: Introductionmentioning

confidence: 99%

“…An example of therapy performance for a head and neck cancer[1] Thermal neutron 5.8 x 10 6 n/sec/cm 2 for 30mA Epi-thermal neutron 8.1 x 10 8 n/sec/cm 2 for 30mA…”

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confidence: 99%

Liquid Li based neutron source for BNCT and science application

Horiike

Murata

Iida

et al. 2015

Applied Radiation and Isotopes

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“…Tritium is generated by the D-Li reaction, and D in the beam of the reaction is contained in the Li loop. The generating rates of hydrogen isotopes (D, T) in the Li are approximately 5,160 and 7 g/year [1]. These hydrogen isotopes have to be recovered from the liquid Li loop for safety, and the tritium concentration is reduced below 1 wppm [2].…”

Section: Introductionmentioning

confidence: 99%

Hydrogen Recovery from Liquid Li with Y Hot Trap

Shigeharu

Hatachi

Hiromoto

et al. 2012

Plasma and Fusion Research

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Materials to compose a fusion reactor chamber are subjected to neutron irradiation. International Fusion Materials Irradiated Facility (IFMIF) will be used to analyze how neutron damage affects material durability. The material is irradiated by high-intensity neutron beam, which is generated by the D-Li stripping reaction. Tritium (T) generated by by-pass reaction needs to be recovered from liquid Li for safety. Recovery of tritium by an yttrium (Y) hot trap is one of the ways to recover T from liquid Li in IFMIF. Therefore, it is necessary to analyze the behavior of T in the liquid Li. In this study, the authors measured H 2 absorption rates under stirred conditions of liquid Li and analyzed the effect of hydrogen absorption rate of Y by elevating temperature from 250• C to 400• C to establish the way to recover T from liquid Li with the Y hot trap in IFMIF. Judging from the comparison, we considered the rate-determining step is H diffusion in Y. Mass transfer coefficients at each temperature were determined by fitting the results between calculation and experiment.

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Latest design of liquid lithium target in IFMIF

Cited by 23 publications

References 13 publications

Nitrogen Hot Trap Design and Manufactures for Lithium Test Loop in IFMIF/EVEDA Project

Nitrogen Hot Trap Design and Manufactures for Lithium Test Loop in IFMIF/EVEDA Project

Liquid Li based neutron source for BNCT and science application

Hydrogen Recovery from Liquid Li with Y Hot Trap

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