Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

DOI： 10.1016/j.jnucmat.2004.11.005

Language：English   Publishing type：Research paper (scientific journal)  

DOI： 10.1016/j.jnucmat.2003.09.002

Publishing type：Research paper (scientific journal)   Publisher：Elsevier BV  

We have proposed tritium (T) production using a high-temperature gas-cooled reactor (HTGR) and explored its application for initial T possession in a demonstration (DEMO) fusion reactor. To maintain T containment within the Li-loading rod throughout the HTGR operation period, Ni-coated Zr spheres are considered as T absorption materials, designed to prevent an increase in internal T partial pressure and secure T retention in the Li-loading rod. This study evaluates the performance of Zr spheres by examining their hydrogen absorption properties within the HTGR environment, where oxides coexist. In addition, the apparent diffusivities and solubilities of hydrogen in Zr are studied at pressures ranging from 80 to 8000 Pa. It is shown that the coexisting oxides cause a reduction in diffusivity but has minimal impact on solubility, the pressure has no significant impact on the hydrogen absorption performance in HTGR environment at 900 °C.

DOI： 10.1016/j.fusengdes.2025.114944

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Publisher：Nuclear Fusion  

Superconducting (SC) tokamak JT-60SA plays an essential role in fusion research and development by supporting and complementing the ITER project, providing directions to the DEMO design activity and fostering next generation scientists and engineers. Since the short circuit incident at the terminal joints of equilibrium field coil #1 during the integrated commissioning (IC) in March 2021, both EU and JA implementing agencies (IAs) have examined how to ensure safe operation of JT-60SA by mitigating the risk of possible discharge occurrence inside the cryostat. Based on the experience of the global Paschen tests, the IAs have established a strategy of risk mitigation measures, which is a combination of (i) reinforcement of insulation, (ii) avoiding unnecessary voltage application to the coil systems and (iii) immediate de-energization of the coils when deteriorated vacuum conditions are detected. Thanks to the considerable efforts of the Integrated Project Team members, the IC restarted in May 2023. After confirmation of the SC state of the coil systems (TF, EF and CS), the coil energization test and the plasma operation phase 1 (OP-1) started. The first plasma was successfully achieved on 23 October 2023 with a limited value of voltage and current applied to the coils. The plasma configuration control was also confirmed with low plasma current and low auxiliary heating power conditions. Based on the IO-F4E-QST collaboration, activities of JT-60SA have been shared with the IO and provided an important lesson for ITER assembly and commissioning, and will provide an outstanding contribution to fusion research at large. After OP-1, maintenance & enhancement phase 1 (M/E-1) starts from January 2024, in which in-vessel components are installed, and heating and diagnostic systems are extensively upgraded to allow a high power heating experiment planned in OP-2. In order to make the best use of JT-60SA, a newly organized JT-60SA experiment team will refine the research plan for the future high heating power operation phase.

DOI： 10.1088/1741-4326/ad34e4

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Publishing type：Research paper (scientific journal)   Publisher：Elsevier BV  

Tritium production using nuclear reactions of neutrons with lithium in a high temperature gas-cooled reactors has been studied as an external source of fuel tritium in the early stage of fusion reactor operation. In order to control tritium migration throughout the reactor, it is important to understand tritium release behaviors from Zr-containing LiAlO2, which are used as tritium producing materials. In this study, tritium release behavior from neutron irradiated LiAlO2 with and without Zr ware investigated by heating to 900 °C. In the case of heating only LiAlO2, most tritium was released in the chemical form of HTO. On the other hand, in the case of heating Zr-containing LiAlO2, the chemical form of tritium was mostly HT. This result indicates that even if tritium is released from LiAlO2 as HTO, it is effectively absorbed by Zr at 900 °C.

DOI： 10.1016/j.fusengdes.2024.114657

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Language：English   Publisher：Applied Radiation and Isotopes  

Immersion, percolation and tritium release experiments in peat and vermiculite soil samples were performed to analyze their behavior in this widely used medium for plant cultivation. Samples were immersed in tritiated water for 696 h and the isotope exchange capacity evaluated. A vertical flow regime was also considered with analysis for hydraulic conductivity to understand tritium mobility and therefore its availability. Peat soil showed a high tritium retention after percolation, but vermiculite seem to suppress its retention ability. The high moisture and organic content of peat enhanced its isotope exchange capacity. The falling head method was used to numerically evaluate the saturated hydraulic conductivity and outflow flux. Calculated isotope exchange capacity was 4.95×10-2 mol-T2O/g for peat and 3.38×10-2 mol-T2O/g for vermiculite. The tritium release experiment showed significant release of tritiated carbons in peat.

DOI： 10.1016/j.apradiso.2024.111344

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PubMed

Publisher：IEEE Transactions on Plasma Science  

Li<inline-formula> <tex-math notation="LaTeX">$_{2}$</tex-math> </inline-formula>TiO<inline-formula> <tex-math notation="LaTeX">$_{3}$</tex-math> </inline-formula> with additional Li is one of the promising materials to attain an overall tritium breeding ratio (TBR) over one to operate deuterium-tritium (DT) fusion power plants. However, unfortunately, some studies have clarified that the additional Li makes it unstable compared to ordinary Li<inline-formula> <tex-math notation="LaTeX">$_{2}$</tex-math> </inline-formula>TiO<inline-formula> <tex-math notation="LaTeX">$_{3}$</tex-math> </inline-formula> pebbles and prone to evaporation as LiOH, causing corrosion damage to the surrounding structural material. Therefore, this work aimed to investigate the Li mass loss behavior of the ceramic pebbles recently developed, Li<inline-formula> <tex-math notation="LaTeX">$_{{2+x}}$</tex-math> </inline-formula>TiO<inline-formula> <tex-math notation="LaTeX">$_{{3+y}}$</tex-math> </inline-formula> <inline-formula> <tex-math notation="LaTeX">$+$</tex-math> </inline-formula> 20 wt% Li<inline-formula> <tex-math notation="LaTeX">$_{2}$</tex-math> </inline-formula>ZrO<inline-formula> <tex-math notation="LaTeX">$_{3}$</tex-math> </inline-formula> (LTZO) through long-term heating experiments. It was concluded that it would eventually lose 1.5 wt% of LTZO as Li<inline-formula> <tex-math notation="LaTeX">$_{2}$</tex-math> </inline-formula>O evaporation loss resulted from the interaction with water vapor. No structural changes due to the long-term heating for up to 30 days were observed through X-ray photoelectron spectroscopy (XPS), X-ray diffraction (XRD), and scanning electron microscopy-energy dispersive X-ray (SEM-EDX). In addition, this work performed a simplified 1-D simulation based on the obtained experimental data. It showed that Li evaporation from the LTZO pebbles was so rapid that the benefits of additional Li for tritium production were limited. In contrast, the corrosion caused by LiOH generated through evaporation would need more attention. Compared to the Li burn-up rate, although this phenomenon would not negatively impact tritium production, Li evaporation would dominate more during the first four months of operation. Finally, several countermeasures were proposed to maximize the benefits of Li addition for tritium production.

DOI： 10.1109/TPS.2024.3391000

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Fusion Science and Technology  

Several fusion plants plan to utilize two high-temperature and high-pressurized water coolant systems. Because of the high hydrogen-isotope mobility in high-temperature metal, tritium will inevitably transfer from the plasma side to the secondary coolant through the primary coolant. From the viewpoints of fuel control, tritium safety, and social acceptance, it is compulsory to investigate the tritium concentration dependence of permeation phenomena experimentally. Therefore, this study conducted a protium permeation experiment instead of tritium, which mocked the situation where the tritium concentration in the primary loop was extremely high. Considering the results in the previous tritium permeation research by the present authors, the tritium permeation behavior was likely proportional to the first power of the tritium concentration. Then, based on these experiments and references regarding the tritium permeation rate and water detritiation system (WDS) design, tritium concentration was computed in both loops. In this calculation condition, the primary and secondary loops reached about 0.4 TBq/kg and 167 MBq/kg during 3-year operations, respectively. Also, it was found that the required feed rate to keep the tritium concentration at 1 TBq/kg was 46.5 kg/h, which is less than the existing WDS specification.

DOI： 10.1080/15361055.2023.2271228

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Fusion Science and Technology  

Hydrogen isotope behavior, especially permeation and retention, at the first wall is important for the safety and fuel sufficiency of fusion reactors. This study focuses on the deposition layer formed on the first wall by sputtered particles. Hydrogen permeation flux was measured under the co-deposition environment of hydrogen and tungsten, and the microstructure of the deposition layer was observed by a transmission electron microscope. Then the relationship between the observed hydrogen permeation behavior and the formation of the deposition layer was evaluated. The results showed that the deposited layers had three different microstructures and that the permeation flux decreased with its formation. However, it was concluded that the permeation behavior could be evaluated simply by the increase in the thickness of the deposited layer and that there was no clear effect of the different structures on the permeation behavior.

DOI： 10.1080/15361055.2024.2306100

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Fusion Science and Technology  

Tritiated water from fusion power reactors will be the next major issue when fusion technology comes fully onstream. Effective radiation protection measures will be implemented when the scope of its behavior is well understood. To understand tritium behavior in the environment, komatsuna was cultivated in tritium-contaminated peat soil. It was indicated experimentally from water immersion experiments that the amount of tissue free water tritium in komatsuna depends on the tritium concentration in the soil and that the concentration in stems and leaves in komatsuna decreases as the tritium concentration in the soil decreases. The amounts of tritium retained in the roots were much less than that in the stems and leaves.

DOI： 10.1080/15361055.2023.2298519

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Nuclear Engineering and Design  

An initial tritium inventory is required to start fusion DEMOnstration Power Station (DEMO) reactors. However, a method to supply adequate tritium has not been determined yet. Tritium production via 6Li(n,α)T reaction by loading Li rods into the burnable poison (BP) holes of a high-temperature gas-cooled reactor (HTGR) has been proposed to address this problem (Matsuura et al., Nucl. Eng. Des. 243 (2012) 95 - 101). In previous preliminary studies, Li rods loaded in all BP holes were assumed to have the same design. This study evaluated whether the performance of Li rods can be improved for future optimization by adjusting the Li rod arrangement and the amount of Li compounds in them. The amount of tritium produced for gas turbine high-temperature reactor 300 (GTHTR300) was evaluated, while the total amount of Li compounds was maintained and the amount of loaded Li compounds changed depending on the layers and fuel regions. The maximum amount of tritium produced did not increase during the evaluations when reactor feasibility was satisfied. This implies that it is possible to reduce the number of Li rods while maintaining the amount of tritium produced for optimization, thereby reducing the costs of manufacturing Li rods and tritium recovery. GTHTR300 can produce 800 g of tritium in 360 days of operation using 2160Li rods. The results showed that the same amount of tritium could be produced by loading 720Li rods with the same number of fuel blocks. In addition, the effective multiplication factor, burn up, and power density of GTHTR300 were not significantly influenced during the operation.

DOI： 10.1016/j.nucengdes.2023.112665

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Publishing type：Research paper (scientific journal)   Publisher：Elsevier BV  

This work proposes tritium (T) production using a high-temperature gas-cooled reactor (HTGR) and studies it for the initial T inventory in a demonstration fusion reactor and a prior engineering test with T handling. At this stage, the aim is to investigate the compatibility between electricity and T production, which makes the stable confinement of T in the Li-loading rods during the HTGR operation period a crucial issue. The total T outflow into the helium gas during the reactor operation period was attempted to be reduced using Zr spheres with Ni coating as a T absorption material to avoid an increase in the inner T pressure. The basic hydrogen absorption properties of the Zr spheres with Ni coating, which coexist in an environment with Al2O3 and/or LiAlO2 oxides, were measured. The structures of the Li-loading rod for a typical commercial HTGR and irradiation test were studied using the obtained data. In addition, an outline of the irradiation test is reported.

DOI： 10.1016/j.fusengdes.2023.114054

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Language：English   Publishing type：Research paper (scientific journal)  

DOI： doi.org/10.3390/separations10110578

Publisher：Separations  

Selective H2 evolution and CO2 absorption in several ethanolamine aqueous solutions are comparatively investigated using a new electrolysis reactor. H2 bubbles are generated from a cathode in any ethanolamine electrolyte, and its experimental gas evolution rates are correlated by Faraday’s first rule. No or smaller amounts of CO2 and N2 bubbles than stoichiometric ones are generated on an anode through the reaction between hydroxide ions and ethanolamine ones. No CO or O2 is observed in the system exhaust, and most of the CO2, along with N2, is still absorbed in ethanolamine aqueous solutions with the addition of KOH and/or HCOOH under high pH conditions. Variations of the concentrations of coexisting ions dissolved in the electrolytes of mono- or tri-ethanolamine (MEA or TEA) and ethylenediamine (EDA) solutions with CO2 absorption are calculated using the equilibrium constants to relate the concentrations of solute ions. Electric resistivities of the ethanolamine aqueous solutions are correlated by the pH value and are analyzed in terms of equilibrium constants among the concentrations of coexisting ions. Conditions of the MEA electrolyte to achieve high-performance electrolysis is discussed for selective H2 generation.

DOI： 10.3390/separations10110578

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Language：English   Publisher：The Japan Society of Plasma Science and Nuclear Fusion Research  

<p>The purpose of the research unit UlCoMat (<u>Ul</u>trahigh-flux <u>Co</u>ncerting <u>Mat</u>erials) is creation of novel materials for advanced engineering systems, such as fusion and fission reactors, aerospace craft, rockets and chemical plants, based on understanding and control of the metastable phase and the self-organization induced in materials under extreme conditions. The UlCoMat will accelerate a paradigm shift from stable and resistant materials to metastable but adaptive ones. It focuses also on the science of life to seek long-life materials and a precise estimation of their existence for the development of robust engineering systems using the minimum materials compatible with economical and safety requirements.</p>

DOI： 10.1585/pfr.18.2505085

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CiNii Research

Language：English   Publishing type：Research paper (scientific journal)   Publisher：Fusion Engineering and Design  

Hydrogen extraction from methane will be a common and useful technique in hydrogen production systems and fuel cycle systems of deuterium-tritium fusion reactors. Since tritium is a precious fuel, it needs to be extracted from impurity gases such as tritiated methane contained in the exhaust gas from the plasma vessel of a fusion reactor. An experimental work was conducted in this study to investigate the electron collision of methane decomposition reaction in helium plasma. A special attention was placed on the electron density distribution in a plasma chamber, and the dependence of the decomposition rate on the methane/helium ratio. The experimental results showed that methane decomposition rate and electron density tended to increase linearly with increasing RF power. This suggests that a strong dependence of electron collision on methane decomposition. Eventually, the dependence of methane decomposition rate on electron density, total pressure, and inlet methane concentration in a gas flow-type helium plasma reactor was successfully formulated. This study provides new sight for demonstrating the contribution of electron density in RF plasma assisted methane decomposition, and the summarized equation offers potential for reactor design on promising energy utilization.

DOI： 10.1016/j.fusengdes.2023.113885

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Fusion Engineering and Design  

DOI： 10.1016/j.fusengdes.2023.113825

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Fusion Engineering and Design  

DOI： 10.1016/j.fusengdes.2023.113791

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Publisher：International Journal of Applied Ceramic Technology  

The long-term thermal stability of tritium breeding materials during service is a key factor to ensure efficient tritium release. In this study, the long-term thermal stability of advanced Li4TiO4–Li2TiO3 core–shell breeding pebbles under continuous heating in 1%H2/Ar at 900°C was investigated for the first time. The results show that this core–shell material loses 3.4% Li mass after heating for 30 days, resulting in a reduction in Li density to.415 g/cm3, which is still significantly higher than other breeding materials. The moisture in the sample bed will determine the form of Li volatilization and thus affect the rate of Li mass loss. The core–shell pebbles maintain favorable phase stability during long-term heating, and the grain sizes of the Li2TO3 shell and Li4TiO4 core after 30 days of heating are 6.5 ± 1.5 and 6.9 ± 2.5 μm, respectively. Moreover, the samples did not crack or collapse during long-term heating and still had a satisfactory crushing strength of 37.61 ± 7.13 N after 30 days of heating. Overall, the high Li density and good thermal stability during long-term heating demonstrate that the Li4TiO4–Li2TiO3 core–shell breeding pebbles are a very reliable tritium breeding material for long-term service under harsh operating conditions.

DOI： 10.1111/ijac.14392

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Publisher：Fusion Engineering and Design  

Li4TiO4 and Li4TiO4-Li2TiO3 core-shell breeding ceramics were considered as promising tritium breeding materials in fusion reactor blanket, and the effect of adsorbed water on the tritium release behavior of these two types of materials was investigated and compared in this study. All samples were first irradiated by thermal neutrons at Kyoto University, followed by out-of-pile tritium release experiments at Kyushu University. It was found that both Li4TiO4 and Li4TiO4-Li2TiO3 core-shell breeding ceramics have two tritium trapping sites, mainly due to the overlapping of the tritium release temperature of Li2TiO3 with the second tritium release site of Li4TiO4. Besides, it was observed that the adsorbed water can slightly reduce the tritium release temperature of the two types of tritium breeding materials. More importantly, the effect of adsorbed water on tritium release form (HT/HTO ratio) was quantitatively studied. The results demonstrate that water adsorption has a significant effect on the tritium release form of the breeding ceramics, and the core-shell structure can inhibit the hygroscopicity of Li4TiO4 to increase the fraction of tritium release in the HT form.

DOI： 10.1016/j.fusengdes.2022.113374

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Language：English   Publisher：Interdisciplinary Graduate School of Engineering Sciences, Kyushu University  

Organically bound tritium (OBT) is radiologically relevant for radiation protection purposes due to its persistence and relatively long effective half-life (80 days). Estimation of doses due to OBT requires analysis of key environmental matrices that serves as pathway for ingestion. Studies on vegetation and soil exposed to tritium or deuterium has been done with models to predict future doses. Tritiated water has been identified as the chemical species of interest due to its ease of incorporation into biological tissues. Estimation of tritium doses has been done with a variety of techniques including Liquid Scintillation Counting, mass spectrometry. Environmental tritium models such as BIOMOVS, BIOMASS and EMRAS has been widely adopted by countries for radiation safety assessment.

DOI： 10.5109/5909112

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CiNii Research

Language：English   Publishing type：Research paper (scientific journal)   Publisher：The Japan Society of Plasma Science and Nuclear Fusion Research  

<p>In a thermonuclear fusion reactor, a fuel cycle system that recovers and reuses unburnt hydrogen isotopes is indispensable. Oxygen (O) and carbon (C) impurities are chemically combined with the unburnt hydrogen isotopes and exhausted from the plasma vessel of the fusion reactor. The impurities must be decomposed in the fuel cycle system to recover the hydrogen isotopes, especially tritium. In this study, a flow-type reactor using a radio-frequency (RF) plasma was applied to decompose water vapor (H₂O) molecules. The effect of C deposition on the vessel wall (stainless steel) was confirmed experimentally to promote reactions relating to the decomposition. At RF powers of 30 - 150 W, the decomposition ratio was around 30% with an argon gas mixed with 5% H₂O at the pressure of 100 Pa (5 Pa for H₂O) and the flow rate of 20 sccm (1 sccm for H₂O). The decomposition was enhanced by C depositions on the vessel wall; the decomposition ratio was largely increased to be 75% at the RF power of 150 W. Reasons for the increased ratio may be a reduction of O atoms and molecules and a production of carbon monoxide through the interaction with C depositions. The reduction of O products promoted the decomposition of H₂O in the plasma because the recombination of O and H can be suppressed.</p>

DOI： 10.1585/pfr.17.2405087

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Nuclear Fusion  

In order to efficiently grasp the tritium behavior in advanced core-shell breeding materials, this study adopts a route of injecting tritium out-of-pile to deal with the problems of fewer platforms, long periods, and high costs for traditional neutron irradiation-tritium release experiments. Here, tritium adsorption and desorption experiments were carried out with Li4TiO4-Li2TiO3 core-shell breeding materials before and after long-term heating up to 30 days. The purpose is to study whether the structural changes caused by long-term heating will affect the adsorption and desorption behavior of tritium on the sample surface. The results show that the lack of chemically adsorbed water caused by long-term heating will significantly weaken the tritium adsorption capacity of the sample, but will not affect the desorption behavior of Ar, 1% H2 + Ar and water vapor on tritium, so all samples show a very low tritium retention.

DOI： 10.1088/1741-4326/ac6434

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Journal of Nuclear Materials  

From a safety standpoint, it is important to understand the behavior of tritium in the coolant of DT fusion reactors. The high-temperature and high-pressure water is expected to be used as a coolant in JA DEMO. Therefore, it is necessary to deepen the understanding of the tritium transfer from the primary cooling water to the secondary cooling water in a heat exchanger. In this study, a double-tube permeation device consisting of Inconel 600 tube, which is a heat exchanger material, and SS316 tube, was assembled and the tritium permeation from tritiated water to water at 300 °C and 17 MPa was observed. Remarkable tritium permeation was observed after around 17 days as the cumulative heating time. Gaseous tritium (HT and T2) was detected in the gas phase of the tritiated water side after the permeation experiments. This suggests that a part of tritium generated in the metal oxidation reaction dissolved in the Inconel and diffused and permeated. With assuming that the diffusion process of tritium through the Inconel was the rate controlling step of permeation, the permeability of tritium through the Inconel tube from the tritiated water derived from the experimental data was 3 orders of magnitude smaller than that obtained from the hydrogen isotope permeation experiments from gas phase to gas phase.

DOI： 10.1016/j.jnucmat.2022.153723

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Publisher：Nuclear Fusion  

Construction of the JT-60SA tokamak was completed on schedule in March 2020. Manufacture and assembly of all the main tokamak components satisfied technical requirements, including dimensional accuracy and functional performances. Development of the plasma heating systems and diagnostics have also progressed, including the demonstration of the favourable electron cyclotron range of frequency (ECRF) transmission at multiple frequencies and the achievement of long sustainment of a high-energy intense negative ion beam. Development of all the tokamak operation control systems has been completed, together with an improved plasma equilibrium control scheme suitable for superconducting tokamaks including ITER. For preparation of the tokamak operation, plasma discharge scenarios have been established using this advanced equilibrium controller. Individual commissioning of the cryogenic system and the power supply system confirmed that these systems satisfy design requirements including operational schemes contributing directly to ITER, such as active control of heat load fluctuation of the cryoplant, which is essential for dynamic operation in superconducting tokamaks. The integrated commissioning (IC) is started by vacuum pumping of the vacuum vessel and cryostat, and then moved to cool-down of the tokamak and coil excitation tests. Transition to the super-conducting state was confirmed for all the TF, EF and CS coils. The TF coil current successfully reached 25.7 kA, which is the nominal operating current of the TF coil. For this nominal toroidal field of 2.25 T, ECRF was applied and an ECRF plasma was created. The IC was, however, suspended by an incident of over current of one of the superconducting equilibrium field coil and He leakage caused by insufficient voltage holding capability at a terminal joint of the coil. The unique importance of JT-60SA for H-mode and high-β steady-state plasma research has been confirmed using advanced integrated modellings. These experiences of assembly, IC and plasma operation of JT-60SA contribute to ITER risk mitigation and efficient implementation of ITER operation.

DOI： 10.1088/1741-4326/ac10e7

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Elsevier BV  

For starting up a fusion reactor stably, the tritium production by the nuclear reaction of neutrons and lithium in a high-temperature gas-cooled reactor has been studied. In order to suppress the migration of tritium to the whole reactor, it is important to design a Li rod with tritium confinement function and understand tritium behavior. A Li rod structure consisting of Zr - LiAlO2 - Zr - Al2O3 was proposed, and an assembly simulating proposed Li rod was fabricated. In the previous work using tritium gas containing mainly HTO rather than HT, the present authors succeeded in confining tritium in the assembly at 700 ℃ for 87 h. In this work, tritium gas containing mainly HT rather than HTO was supplied to the assembly, tritium permeation behavior was observed. Unlike the case of HTO, tritium permeated immediately after the introduction of HT. This result indicates that the chemical form of tritium significantly affects tritium confinement performance of the Li rod.

DOI： 10.1016/j.nme.2022.101170

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Language：English   Publishing type：Research paper (scientific journal)   Publisher：Nuclear Engineering and Design  

Tritium is required for research and development activities for the deuterium–tritium (DT) fusion reactor and fueling the DEMOnstration Power Station (DEMO). However, tritium is a very rare nuclide and must be produced artificially. Tritium production by loading Li compounds (Li rods) into burnable poison holes of a high-temperature gas-cooled reactor (HTGR) has been proposed (H. Matsuura, et al., Nucl. Eng. Des. 243 (2012) 95–101.). Al2O3 and Zr are used to prevent tritium leaks. Nuclear reaction heat caused by the nuclear reaction (e.g., 6Li(n,α)T reaction) can cause a spatial temperature profile in the Li rods and may change its tritium containment performance, because Al2O3 and Zr performance strongly depend on these temperatures. The effect of nuclear reaction heat by the 6Li(n,α)T reaction on the tritium containment performance of the Li rods was evaluated by simulation. The temperatures of the Li rods for the high-temperature engineering test reactor (HTTR) and gas turbine high-temperature reactor 300 (GTHTR300) increased by 36 K and 46 K, and the leaked tritium decreased by 32% and 37% via nuclear reaction heat, respectively.

DOI： 10.1016/j.nucengdes.2021.111584

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DOI： 10.1016/j.fusengdes.2021.112851

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DOI： 10.1016/j.fusengdes.2021.112787

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DOI： 10.1016/j.fusengdes.2021.112576

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DOI： https://doi.org/10.1016/j.fusengdes.2021.112495

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DOI： https://doi.org/10.1016/j.fusengdes.2021.112558

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DOI： https://doi.org/10.1016/j.fusengdes.2021.112441

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DOI： https://doi.org/10.1016/j.fusengdes.2021.112372

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DOI： https://doi.org/10.1016/j.fusengdes.2020.112083

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DOI： https://doi.org/10.1016/j.fusengdes.2020.112011

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DOI： https://doi.org/10.1016/j.nme.2020.100777

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DOI： 10.1080/15361055.2020.1728175

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DOI： https://doi.org/10.1016/j.fusengdes.2019.03.174

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Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

It is important to understand tritium desorption behavior from plasma-facing materials of a fusion reactor in order to discuss effective tritium recovery method from in-vessel components. However, basic behavior of hydrogen isotopes in W deposition layer is not understood completely. In this study, characterized tungsten deposition layer formed by hydrogen plasma sputtering was exposed to gaseous tritium at 300 °C or 500 °C and tritium desorption behavior by vacuum heating was investigated by the imaging plate technique. For comparison, bare tungsten substrates were exposed to gaseous tritium in the same condition. Initial tritium activity in the deposition layer was much higher than that in the bare substrate. Tritium desorption behavior from tungsten deposition layer was different by the temperature of the layer during tritium exposure process. By heating at 500 °C for 1 h, 97.5% of tritium was desorbed from the layer exposed to tritium at 300 °C. On the other hand, by heating at 500 °C for 2 h, only 44.6% of tritium was desorbed from the layer exposed to tritium at 500 °C. To recover most tritium from W deposition layer and W substrate, heating at above 700 °C is required.

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

To consider carbon balance and hydrogen isotope balance in the fuel cycle system and tritium safety management of a fusion reactor, the evaluation of carbon and hydrogen isotope accumulation not only in the vacuum vessel but also in the exhaust system is necessary. In the present work, type 316 stainless steel substrates were installed at 4 locations in the exhaust duct of the Large Helical Device (LHD) during the 13th experimental campaign. By using the combustion method, the amount of carbon slightly adhering to the substrates, which cannot be measured by electric microbalances, was successfully quantified to be 2 g/cm2. The hydrogen release behavior from the substrate was consistent with that from carbon deposition layer formed by hydrogen plasma sputtering. H/C ratio on the substrate was estimated to be about 1-1.5. Hydrogen incorporated into the metal deposit formed from type 316 stainless steel in the sputtering-deposition device in the laboratory can remain in the deposit even under high vacuum condition in the exhaust duct for a long period.

Language：English   Publishing type：Research paper (scientific journal)  

In this study, weight reduction of Li2TiO3 with excess Li and Li4SiO4 at elevated temperatures under hydrogen atmosphere or water vapor atmosphere were investigated. The Li mass loss for the Li2TiO3 at 900 oC was 0.4 wt% under 1000 Pa H2 atmosphere and 1.5 wt% under 50 Pa H2O atmosphere. The Li mass loss for the Li2TiO3 increased proportionally to the water vapor pressure in the range from 50 to 200 Pa at 900 oC and increased with increasing temperature from 700 to 900 oC although Li mass loss at 600 oC was significantly smaller than expected. It was found that water vapor concentration dependence and temperature dependence of Li mass loss for the Li2TiO3 and the Li4SiO4 used in this work were quite different. Water vapor is released from the ceramic breeder materials into the purge gas due to desorption of adsorbed water and water formation reaction. The released water vapor possibly promotes Li mass loss with the formation of LiOH on the surface.

Language：English   Publishing type：Research paper (scientific journal)  

It is important to evaluate the influence of deposition layers formed on plasma facing wall on tritium permeation and tritium retention in the vessel of a fusion reactor from a viewpoint of safety. In this work, tungsten deposition layers having different thickness and porosity were formed on circular nickel plates by hydrogen RF plasma sputtering. Hydrogen permeation experiment was carried out at the temperature range from 250 oC to 500 oC and at hydrogen pressure range from 1013Pa to 101300Pa. The hydrogen permeation flux through the nickel plate with tungsten deposition layer was significantly smaller than that through a bare nickel plate. This indicates that a rate-controlling step in hydrogen permeation was not permeation through the nickel plate but permeation though the deposition layer. The pressure dependence on the permeation flux differed by temperature. Hydrogen permeation flux through tungsten deposition layer is larger than that through tungsten bulk. From analysis of the permeation curves, it was indicated that hydrogen diffusivity in tungsten deposition layer is smaller than that in tungsten bulk and the equilibrium hydrogen concentration in tungsten deposition layer is enormously larger than that in tungsten bulk at same hydrogen pressure.

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

The influence of the deposition conditions on hydrogen incorporation into metal deposits was investigated by exposing tungsten (W) or stainless steel (SS) to hydrogen and argon mixed plasma. The sputtering yield of SS was lower than expected from a sputtering yield of iron and was close to that of Mo. The hydrogen incorporated into W deposits was released by heating up to 600 oC. On the other hand, the release of hydrogen from SS deposits continued until 1000 oC. The H/W ratio in W deposits decreased with decreasing the H/W flux ratio toward the growing surface and increasing substrate temperature. The H/W ratio in W deposit formed at at 500 oC was 0.005. The H/Metal ratio in SS deposits was varied in the range between 0.03 and 0.3 depending on the target bias but the influences of the H/Metal flux ratio and substrate temperature were not observed.

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

It has been known that water vapor is released from ceramic breeder materials into the purge gas due to desorption of adsorbed water under dry atmosphere and due to the water formation reaction under hydrogen atmosphere. However, an effect of water vapor in the purge gas to Li mass loss has not been understood. In this study, mass loss of Li2TiO3 (NFI) and Li4SiO4 (FzK) under hydrogen atmosphere (1000 Pa H2/Ar), and mass loss of Li2TiO3 (NFI) and Li2TiO3 with additional Li which is in a developmental stage (JAEA) under water vapor atmosphere (50 Pa H2O/Ar) were compared, respectively. It was found that under hydrogen atmosphere Li mass loss of Li4SiO4 and Li2TiO3 is same degree although the amount of water vapor released from Li4SiO4 is larger than that from Li2TiO3. It was clarified with regard to Li2TiO3 that Li mass loss in water vapor atmosphere is larger than that in hydrogen atmosphere. Mass loss of Li2TiO3 with additional Li (JAEA) was larger than that of Li2TiO3 (NFI). It was observed by X-ray analysis that Li deposits formed on the inner wall of the quartz tube contain Li2SiO3.

Language：English   Publishing type：Research paper (scientific journal)  

Tritium sorption capacity is an important parameter to evaluate tritium behavior on lithium ceramic breeder materials. In the present study, sorption and desorption behavior of tritiated water on Li2TiO3 with additional Li, which is in a developmental stage in Japan Atomic Energy Agency as an advanced tritium breeder materials, was observed at 20 oC, 300 oC, 600 oC, 900 oC. Tritium sorption capacity on Li2TiO3 with additional Li is larger than that on Li2TiO3. At 600 oC and 900 oC, the sorption capacity approximately agrees with the sum of physical adsorption capacity and chemical adsorption capacity, but at 20 oC and 300 oC it is smaller than that. The overall mass transfer coefficient for tritium sorption increases with temperature in the range from 20 oC to 600 oC but it decreases considerably at 900 oC. The sorption capacity and the mass transfer coefficient at 600 oC for the sample once used in sorption and desorption experiment at 900 oC are smaller than that for original ones.

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Release behavior of water vapor and mass loss from lithium titanate

Language：English   Publishing type：Research paper (scientific journal)  

Release behavior of water vapor and mass loss from lithium titanate

Language：English   Publishing type：Research paper (scientific journal)  

Release behavior of water vapor and mass loss from lithium titanate

Language：English   Publishing type：Research paper (scientific journal)  

Effect of hydrophobic paints coating for tritium reduction in concrete materials

Language：English   Publishing type：Research paper (scientific journal)  

Sorption and desorption behavior of hydrogen isotopes from tungsten deposits caused by deuterium gas or deuterium plasma exposure

Language：English   Publishing type：Research paper (scientific journal)  

Effects of Preadsorbed H2O and CH4 on H2 and He Adsorption on Activated Carbon at Cryogenic Temperature

Language：English   Publishing type：Research paper (scientific journal)  

Transfer of tritium in concrete coated with hydrophobic paints

Language：English   Publishing type：Research paper (scientific journal)  

A Study on Carbon and Hydrogen Co-Deposition Behavior in Methane-Hydrogen Mixed Plasma

Language：English   Publishing type：Research paper (scientific journal)  

Demonstration of Tritium Extraction from Tritiated Methane in Helium by Utilizing Plasma Decomposition

Language：English   Publishing type：Research paper (scientific journal)  

Study on Tritium Release Behavior from Li2ZrO3

Language：English   Publishing type：Research paper (scientific journal)  

Hydrogen incorporation in tungsten deposits growing by deuterium plasma sputtering

Language：English   Publishing type：Research paper (scientific journal)  

An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

Language：English   Publishing type：Research paper (scientific journal)  

Tritium transfer in porous concrete materials coated with hydrophobic paints

Language：English   Publishing type：Research paper (scientific journal)  

Effect of Water Formation Reaction on Tritium Release Behavior from Li4SiO4

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

DOI： 10.1016/j.tsf.2003.12.030

Language：English   Publishing type：Research paper (scientific journal)  

DOI： 10.1016/S0920-3796(02)00102-3

Language：English   Publishing type：Research paper (scientific journal)  

DOI： 10.3327/jnst.39.371

Language：English   Publishing type：Research paper (scientific journal)  

Event date： 2025.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2025.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2025.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：岐阜県土岐市（核融合科学研究所）   Country：Japan  

Event date： 2025.2

Language：English   Presentation type：Oral presentation (general)  

Venue：Oak Ridge National Laboratory   Country：United States  

Event date： 2025.2

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2025.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：岐阜県土岐市（核融合科学研究所）   Country：Japan  

Event date： 2025.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：岐阜県土岐市（核融合科学研究所）   Country：Japan  

Event date： 2025.1

Language：English   Presentation type：Oral presentation (general)  

Venue：Busan   Country：Korea, Republic of  

Event date： 2025.1

Language：English   Presentation type：Oral presentation (general)  

Venue：Busan   Country：Korea, Republic of  

Event date： 2025.1

Language：Japanese   Presentation type：Poster presentation  

Venue：青森県六ケ所村（QST六ヶ所研究所）   Country：Japan  

Event date： 2025.1

Language：Japanese   Presentation type：Poster presentation  

Venue：青森県六ケ所村（QST六ヶ所研究所）   Country：Japan  

Event date： 2025.1

Language：Japanese   Presentation type：Poster presentation  

Venue：青森県六ケ所村（QST六ヶ所研究所）   Country：Japan  

Event date： 2025.1

Language：Japanese   Presentation type：Poster presentation  

Venue：青森県六ケ所村（QST六ヶ所研究所）   Country：Japan  

Event date： 2025.1

Language：Japanese   Presentation type：Poster presentation  

Venue：青森県六ケ所村（QST六ヶ所研究所）   Country：Japan  

Event date： 2025.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2024.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：福岡市（西新プラザ）   Country：Japan  

Event date： 2024.12

Language：Japanese   Presentation type：Poster presentation  

Venue：福岡市（西新プラザ）   Country：Japan  

Event date： 2024.12

Language：Japanese   Presentation type：Poster presentation  

Venue：福岡市（西新プラザ）   Country：Japan  

Event date： 2024.12

Language：Japanese   Presentation type：Poster presentation  

Venue：福岡市（西新プラザ）   Country：Japan  

Event date： 2024.12

Language：Japanese   Presentation type：Poster presentation  

Venue：福岡市（西新プラザ）   Country：Japan  

Event date： 2024.11

Language：Japanese   Presentation type：Poster presentation  

Venue：東京都江戸川区（タワーホール船堀）   Country：Japan  

Event date： 2024.11

Language：Japanese   Presentation type：Poster presentation  

Venue：東京都江戸川区（タワーホール船堀）   Country：Japan  

Event date： 2024.11

Language：Japanese   Presentation type：Poster presentation  

Venue：東京都江戸川区（タワーホール船堀）   Country：Japan  

Event date： 2024.11

Language：Japanese   Presentation type：Poster presentation  

Venue：東京都江戸川区（タワーホール船堀）   Country：Japan  

Event date： 2024.11

Language：Japanese   Presentation type：Poster presentation  

Venue：東京都江戸川区（タワーホール船堀）   Country：Japan  

Event date： 2024.9

Language：English   Presentation type：Poster presentation  

Venue：Dublin   Country：Ireland  

Event date： 2024.9

Language：English   Presentation type：Poster presentation  

Venue：Dublin   Country：Ireland  

Event date： 2024.9

Language：English   Presentation type：Poster presentation  

Venue：Dublin   Country：Ireland  

Event date： 2024.9

Language：English   Presentation type：Poster presentation  

Venue：Dublin   Country：Ireland  

Event date： 2024.9

Language：English   Presentation type：Poster presentation  

Venue：Dublin   Country：Ireland  

Event date： 2024.9

Language：English   Presentation type：Poster presentation  

Venue：Dublin   Country：Ireland  

Event date： 2024.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：仙台市（東北大学川内北キャンパス）   Country：Japan  

Event date： 2024.9

Language：Japanese   Presentation type：Poster presentation  

Venue：仙台市（東北大学川内北キャンパス）   Country：Japan  

Event date： 2024.9

Language：Japanese   Presentation type：Poster presentation  

Venue：仙台市（東北大学川内北キャンパス）   Country：Japan  

Event date： 2024.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：仙台市（東北大学川内北キャンパス）   Country：Japan  

Event date： 2024.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：仙台市（東北大学川内北キャンパス）   Country：Japan  

Event date： 2024.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：仙台市（東北大学川内北キャンパス）   Country：Japan  

Event date： 2024.9

Language：English   Presentation type：Oral presentation (general)  

Country：Japan  

Event date： 2024.8

Language：English   Presentation type：Oral presentation (general)  

Venue：福岡県春日市   Country：Japan  

Event date： 2024.6

Language：Japanese   Presentation type：Poster presentation  

Venue：八戸市   Country：Japan  

Event date： 2024.6

Language：Japanese   Presentation type：Poster presentation  

Venue：八戸市   Country：Japan  

Event date： 2024.6

Language：Japanese   Presentation type：Poster presentation  

Venue：八戸市   Country：Japan  

Event date： 2024.5

Language：English   Presentation type：Poster presentation  

Venue：Marseille, France   Country：France  

Event date： 2024.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：近畿大学東大阪キャンパス   Country：Japan  

Event date： 2024.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：近畿大学東大阪キャンパス   Country：Japan  

Event date： 2024.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：近畿大学東大阪キャンパス   Country：Japan  

Event date： 2024.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：近畿大学東大阪キャンパス   Country：Japan  

Event date： 2024.3

Language：Japanese  

Venue：近畿大学東大阪キャンパス   Country：Japan  

Event date： 2024.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：近畿大学東大阪キャンパス   Country：Japan  

Event date： 2024.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：九州大学筑紫キャンパス   Country：Japan  

Event date： 2024.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：核融合科学研究所   Country：Japan  

Event date： 2023.12

Language：Japanese  

Venue：福岡市   Country：Japan  

Event date： 2023.12

Language：Japanese  

Venue：福岡市   Country：Japan  

Event date： 2023.12

Language：Japanese  

Venue：福岡市   Country：Japan  

Event date： 2023.12

Language：Japanese  

Venue：福岡市   Country：Japan  

Event date： 2023.12

Language：Japanese  

Venue：福岡市   Country：Japan  

Event date： 2023.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：福岡市   Country：Japan  

Event date： 2023.11 - 2022.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：盛岡市   Country：Japan  

Event date： 2023.11 - 2022.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：盛岡市   Country：Japan  

Event date： 2023.11 - 2022.11

Language：Japanese  

Venue：盛岡市   Country：Japan  

Event date： 2023.9

Language：English  

Venue：Las Palmas de Gran Canaria   Country：Spain  

Event date： 2023.9

Language：English  

Venue：Las Palmas de Gran Canaria   Country：Spain  

Event date： 2023.9

Language：English  

Venue：Las Palmas de Gran Canaria   Country：Spain  

Event date： 2023.9

Language：English  

Venue：Las Palmas de Gran Canaria   Country：Spain  

Event date： 2023.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：名古屋大学東山キャンパス   Country：Japan  

Event date： 2023.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：名古屋大学東山キャンパス   Country：Japan  

Event date： 2023.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：名古屋大学東山キャンパス   Country：Japan  

Event date： 2023.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：名古屋大学東山キャンパス   Country：Japan  

Event date： 2023.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：名古屋大学東山キャンパス   Country：Japan  

Event date： 2023.8 - 2023.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：沖縄県名護市   Country：Japan  

Event date： 2023.7

Language：English  

Venue：Examination Schools, Oxford   Country：United Kingdom  

Event date： 2023.7

Language：English  

Venue：Examination Schools, Oxford   Country：United Kingdom  

Event date： 2023.6

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：伊都キャンパス   Country：Japan  

Event date： 2023.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東京大学駒場キャンパス   Country：Japan  

Event date： 2023.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東京大学駒場キャンパス   Country：Japan  

Event date： 2023.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東京大学駒場キャンパス   Country：Japan  

Event date： 2023.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東京大学駒場キャンパス   Country：Japan  

Event date： 2023.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東京大学駒場キャンパス   Country：Japan  

Event date： 2023.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東京大学駒場キャンパス   Country：Japan  

Event date： 2023.2

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：核融合科学研究所   Country：Japan  

Event date： 2023.2

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：核融合科学研究所+オンライン   Country：Japan  

Event date： 2023.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：大阪大学レーザー科学研究所   Country：Japan  

Event date： 2023.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：JAEA東京事務所   Country：Japan  

Event date： 2023.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：青森県上北郡六ヶ所村（オンライン）   Country：Japan  

Event date： 2023.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：青森県上北郡六ヶ所村   Country：Japan  

Event date： 2022.12

Language：Japanese  

Venue：福岡市   Country：Japan  

Event date： 2022.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：福岡市   Country：Japan  

Event date： 2022.12

Language：Japanese  

Venue：福岡市   Country：Japan  

Event date： 2022.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山市   Country：Japan  

Event date： 2022.11

Language：English   Presentation type：Oral presentation (general)  

Venue：富山市   Country：Japan  

Event date： 2022.11

Language：Japanese  

Venue：富山市   Country：Japan  

Event date： 2022.11

Language：Japanese  

Venue：富山市   Country：Japan  

Event date： 2022.10

Language：English   Presentation type：Oral presentation (general)  

Venue：福岡県春日市   Country：Japan  

Event date： 2022.10

Language：English   Presentation type：Oral presentation (general)  

Venue：対面&オンライン   Country：Romania  

Event date： 2022.10

Language：English  

Venue：対面&オンライン   Country：Romania  

Event date： 2022.10

Language：English  

Venue：対面&オンライン   Country：Romania  

Event date： 2022.10

Language：English   Presentation type：Oral presentation (general)  

Venue：対面&オンライン   Country：Romania  

Event date： 2022.10

Language：English  

Venue：対面&オンライン   Country：Romania  

Event date： 2022.10

Language：English  

Venue：対面&オンライン   Country：Romania  

Event date： 2022.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：対面&オンライン   Country：Croatia  

Event date： 2022.9

Language：English  

Venue：対面&オンライン   Country：Croatia  

Event date： 2022.9

Language：English  

Venue：対面&オンライン   Country：Croatia  

Event date： 2022.9

Language：English  

Venue：対面&オンライン   Country：Croatia  

Event date： 2022.9

Language：English  

Venue：対面&オンライン   Country：Croatia  

Event date： 2022.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese   Presentation type：Symposium, workshop panel (public)  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.7

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.3

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.3

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.1

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2022.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2022.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese   Presentation type：Symposium, workshop panel (public)  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.11

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.10

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2021.10

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2021.10

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2021.10

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.3

Language：English   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2021.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：English   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：English   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2020.12

Language：Japanese  

Venue：オンライン   Country：Japan  

Event date： 2020.11

Language：English   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.11

Language：English   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.11

Language：English   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.11

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.11

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.11

Language：English   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.10

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：English  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.5

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

ヘリカル型核融合原型炉FFHR-d1設計では、溶融塩FLiNaBeブランケットと超臨界CO2二次冷却系によるガスタービン発電システムが採用されている。しかしながら、超臨界CO2環境下でのトリチウム挙動に関する研究はほとんどなく、安全性の観点から、高温高圧CO2と金属界面でのトリチウム挙動の理解が不可欠である。本研究では、国内初となるトリチウムが使用可能な超臨界CO2装置を用いた初期の結果について報告する。

Event date： 2020.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：福島大学   Country：Japan  

Event date： 2020.3

Language：English   Presentation type：Oral presentation (general)  

Venue：福島大学   Country：Japan  

Event date： 2020.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：福島大学   Country：Japan  

Event date： 2020.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：福島大学   Country：Japan  

Event date： 2020.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：福島大学   Country：Japan  

Event date： 2020.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山大学水素同位体科学研究センター   Country：Japan  

Event date： 2020.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：NIFS   Country：Japan  

Event date： 2020.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：JAEA東京事務所   Country：Japan  

Event date： 2019.12

Language：Japanese  

Venue：別府国際コンベンションセンター   Country：Japan  

Event date： 2019.12

Language：Japanese  

Venue：九州大学西新プラザ   Country：Japan  

Event date： 2019.12

Language：Japanese  

Venue：九州大学西新プラザ   Country：Japan  

Event date： 2019.12

Language：Japanese  

Venue：九州大学西新プラザ   Country：Japan  

Event date： 2019.11 - 2019.12

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：中部大学春日井キャンパス   Country：Japan  

Event date： 2019.11 - 2019.12

Language：English  

Venue：中部大学春日井キャンパス   Country：Japan  

Event date： 2019.11 - 2019.12

Language：Japanese  

Venue：中部大学春日井キャンパス   Country：Japan  

Event date： 2019.11 - 2019.12

Language：Japanese  

Venue：中部大学春日井キャンパス   Country：Japan  

Event date： 2019.11 - 2019.12

Language：Japanese  

Venue：中部大学春日井キャンパス   Country：Japan  

Event date： 2019.11 - 2019.12

Language：Japanese  

Venue：中部大学春日井キャンパス   Country：Japan  

Event date： 2019.11

Language：English   Presentation type：Oral presentation (general)  

Venue：SINAP, Shanghai, China   Country：China  

Event date： 2019.11

Language：English   Presentation type：Oral presentation (general)  

Venue：Shanghai Jiao Tong University, Shanghai, China   Country：China  

Event date： 2019.11

Language：English  

Venue：Shanghai Jiao Tong University, Shanghai, China   Country：China  

Event date： 2019.11

Language：English   Presentation type：Oral presentation (general)  

Venue：Shanghai Jiao Tong University, Shanghai, China   Country：China  

Event date： 2019.11

Language：English  

Venue：Ceratopia Toki, Toki-city, Gifu, Japan   Country：Japan  

Event date： 2019.11

Language：English   Presentation type：Public lecture, seminar, tutorial, course, or other speech  

Venue：カリフォルニア大学バークレー校   Country：United States  

燃料自己補給型の核融合炉や、溶融塩炉の安全運転には、冷却材や固体構造材料におけるトリチウム化学や物質移動現象の理解が不可欠である。核融合炉の連続運転には、トリチウムの生産や、同位体分離、トリチウム回収などが重要となる。また、核融合炉や溶融塩炉の安全性には、トリチウムの安全な取り扱いが必須である。本講義では、九州大学を中心とする日本でのトリチウム研究の動向を紹介するとともに、九州大学において得られた溶融塩やグラファイト材料におけるトリチウム挙動研究の成果を説明し、物質移動現象の理解とモデル化について議論する．開催日時は2019年11月1日11:00-12:00、場所は179Stanley Hall.

Event date： 2019.10 - 2019.11

Language：English  

Venue：The Hyatt Regency Hotel, La Jolla Village, California, USA   Country：United States  

Event date： 2019.10 - 2019.11

Language：English  

Venue：The Hyatt Regency Hotel, La Jolla Village, California, USA   Country：United States  

Event date： 2019.10 - 2019.11

Language：English  

Venue：The Hyatt Regency Hotel, La Jolla Village, California, USA   Country：United States  

Event date： 2019.10

Language：English   Presentation type：Oral presentation (general)  

Venue：Okinawa Industry Support Centerungary   Country：Japan  

Event date： 2019.9

Language：English  

Venue：Budapest, Hungary   Country：Hungary  

Event date： 2019.9

Language：English  

Venue：Budapest, Hungary   Country：Hungary  

Event date： 2019.9

Language：English  

Venue：Budapest, Hungary   Country：Hungary  

Event date： 2019.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山大学五福キャンパス   Country：Japan  

Event date： 2019.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山大学五福キャンパス   Country：Japan  

Event date： 2019.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山大学五福キャンパス   Country：Japan  

Event date： 2019.6

Language：English   Presentation type：Oral presentation (general)  

Venue：NIFS, Japan   Country：Japan  

Event date： 2019.4

Language：English   Presentation type：Oral presentation (general)  

Venue：Chikushi campus, Kyushu University   Country：Japan  

Event date： 2019.4

Language：English   Presentation type：Oral presentation (general)  

Venue：Haeundae Grand Hotel, Busan, Korea   Country：Korea, Republic of  

Event date： 2019.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：茨城大学水戸キャンパス   Country：Japan  

Event date： 2019.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：茨城大学水戸キャンパス   Country：Japan  

Event date： 2019.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山大学五福キャンパス   Country：Japan  

Event date： 2019.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：九州大学伊都キャンパス   Country：Japan  

Event date： 2019.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：核融合科学研究所   Country：Japan  

Event date： 2019.1

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：JAEA東京事務所   Country：Japan