Tritium release from molten salt FLiNaK under low flux neutron irradiation with an AmBe neutron source

Kumagai, Kohki; Tanaka, Teruya; Yagi, Juro; Watanabe, Takashi; Sato, F.; Tamaki, Shunsuke; Murata, Isao; Sagara, A.

doi:10.1016/j.fusengdes.2018.04.115

Cited by 3 publications

(5 citation statements)

References 9 publications

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“…soluble. That was similar to the result for the previous irradiation experiments on FLiNaK in which most of the tritium recovered was the released tritium and soluble [6]. A larger amount of insoluble HT was expected to be recovered from FLiNaBe than from FLiNaK because of a smaller amount of free F − ions in FLiNaBe forming clusters, e.g., BeF 2− 4 and Be 2 F 3− 7 , due to the high reducibility of Be [17,18].…”

Section: Chemical Forms Of Tritium Recovered From Flinabesupporting

confidence: 87%

“…Table 1 shows the overall mass transfer coefficients for FLiNaBe at 773 K obtained with the curve fitting, where K 1 and K 2 are the coefficients for the released tritium and the permeated tritium, respectively. The table also shows the results for FLiNaK at 773 K obtained in the previous study [6]. There was no significant difference between the overall mass transfer coefficients for FLiNaBe and FLi-NaK.…”

Section: Comparison Of the Overall Mass Transfer Coefficients For Trimentioning

confidence: 60%

“…In the present study, the overall mass transfer coeffiauthor's e-mail: kumagai.kohki@nifs.ac.jp cients for tritium release from molten FLiNaBe at 673 K and 773 K were evaluated by conducting the neutron irradiation until the tritium release rate reached a steady state. In our previous study, the overall mass transfer coefficients for molten FLiNaK have already been evaluated at 773 K with the AmBe neutron source [6]. The overall mass transfer coefficient for tritium release from a molten salt is considered to be related to the diffusivity of tritium in a molten salt and a gas phase, and the solubility of tritium in a molten salt [7].…”

Section: Introductionmentioning

confidence: 99%

“…Each material was mixed and melted in the Inconel 600 crucible in Ar (5N) atmosphere in a glove box at Kyushu University. The details of the molten salt container and the setting position of the AmBe neutron source are described in the previous paper [6]. The FLiNaBe container consisted of an Inconel 600 crucible, Inconel 600 sheathed thermocouples, a flexible heater, a heat transfer compound, and a thermal insulator.…”

Section: Introductionmentioning

confidence: 99%

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Tritium Release from Molten FLiNaBe under Low Flux Neutron Irradiation

Kumagai

Tanaka

Nagasaka

et al. 2019

Plasma and Fusion Research

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Release behaviors of tritium from molten FLiNaBe (LiF-NaF-BeF 2 ) have been examined in a series of low flux neutron irradiation experiments with an AmBe neutron source at the OKTAVIAN facility of Osaka University. Tritium released from FLiNaBe is swept by He and Ar gases, and recovered by water bubblers. The recovery rate of tritium released from 300 cm 3 of FLiNaBe was 58.0 mBq/h in a steady state, and it was close to the tritium production rate of 58.0 mBq/h calculated by the MCNP6 code. The values of the overall mass transfer coefficients for tritium release from FLiNaBe were close to those for FLiNaK (LiF-NaF-KF) at 773 K. The influence of the diffusivity and the solubility of tritium on the overall mass transfer coefficients has been examined on molten FLiNaBe.

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Section: Chemical Forms Of Tritium Recovered From Flinabesupporting

confidence: 87%

Section: Comparison Of the Overall Mass Transfer Coefficients For Trimentioning

confidence: 60%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Tritium Release from Molten FLiNaBe under Low Flux Neutron Irradiation

Kumagai

Tanaka

Nagasaka

et al. 2019

Plasma and Fusion Research

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“…Figure 3 shows the schematic of a tritium sampler system, which is composed of an Ar gas flow system, a closed stainless-steel container, an electric furnace, and water bubbling tubes [25][26][27]. The core sample weighing approximately 8 g in the closed, stainless-steel container was heated by an electric furnace at 400 • C flowing Ar gas.…”

Section: Tritium Measurementmentioning

confidence: 99%

Radioactivation Analysis of Concrete Wall in OKTAVIAN Facility

Tamaki

Panuntun

UEDOI

et al. 2022

Plasma and Fusion Research

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A deuterium-tritium (DT) neutron generator in Osaka University with a continuous intense neutron source emitting 3 × 10 12 fusion neutrons per second has been in operation since 1981. However, radioactivation for the parts of the accelerator body is a serious issue. Hence, in this study, we investigated the radioactivation of the intense irradiation room containing the continuous intense neutron source. Core samples of the concrete wall were collected at various positions in the irradiation room and the radionuclides in them were determined by performing gamma-ray spectrometry. Major long-lived radionuclides found were 54 Mn, 60 Co, and 152 Eu. The radioactivity of 152 Eu may possibly be consistent with the result obtained using the simulation code. The radioactivities of 54 Mn and 60 Co were minimal compared with that of 152 Eu. The tritium amount in the core sample was measured employing a tritium sampling system and a liquid scintillation detector and was found to be considerably larger than the amount estimated using the simulation code. Tritium diffused from the titanium-tritium target was attached to the wall surface. However, most of it did not penetrate the concrete wall. These results reveal the radioactivity issue of fusion neutron generator facilities and are expected to aid in the maintenance of their operation.

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