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Journal Articles

Study on chemical form of tritium in coolant helium of high temperature gas-cooled reactor with tritium production device

Hamamoto, Shimpei; Ishitsuka, Etsuo; Nakagawa, Shigeaki; Goto, Minoru; Matsuura, Hideaki*; Katayama, Kazunari*; Otsuka, Teppei*; Tobita, Kenji*

Proceedings of 2021 International Congress on Advances in Nuclear Power Plants (ICAPP 2021) (USB Flash Drive), 5 Pages, 2021/10

Impurity concentrations of hydrogen and hydride in the coolant were investigated in detail for the HTTR, a block type high-temperature gas reactor owned by Japan. As a result, it was found that CH$$_{4}$$ was 1/10 of H$$_{2}$$ concentration, which was under the conventional detection limit. If the ratio of H$$_{2}$$ to CH$$_{4}$$ in the coolant is the same as the ratio of HT to CH$$_{3}$$T, the CH$$_{3}$$T has a larger dose conversion factor, and this compositional ratio is an important finding for the optimal dose evaluation. Further investigation of the origin of CH$$_{4}$$ suggested that CH$$_{4}$$ was produced as a result of a thermal equilibrium reaction rather than being released as an impurity from the core.

Journal Articles

Application of tritium tracer techniques to observation of hydrogen on surface and in bulk of F82H

Otsuka, Teppei*; Tanabe, Tetsuo*; Tokunaga, Kazutoshi*; Yoshida, Naoaki*; Ezato, Koichiro; Suzuki, Satoshi; Akiba, Masato

Journal of Nuclear Materials, 417(1-3), p.1135 - 1138, 2011/10

 Times Cited Count:2 Percentile:18.37(Materials Science, Multidisciplinary)

Oral presentation

Tritium production and containment performance of lithium rod test module for high temperature gas-cooled reactor

Ida, Yuma*; Matsuura, Hideaki*; Nagasumi, Satoru*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki

no journal, , 

JAEA and Kyushu University have studied the tritium production method using high temperature gas-cooled reactors (HTGR) for initial fusion reactors. In this method, lithium compounds are loaded into the reactor core and tritium is produced with $$^{6}$$Li(n,$$alpha$$)T reaction. We studied about optimization of lithium loading method, effective tritium containment method and nuclear thermal design of lithium loaded HTGR, and consequently we confirmed the feasibility of the tritium production method. Then, we started preliminary study for lithium irradiation experiment by test reactors. This paper describes evaluation results of tritium production and tritium containment for proposed lithium irradiation capsule.

Oral presentation

Current study and future progress for tritium production method using high temperature gas cooled reactor, 1; Outline of study on tritium production using high-temperature gas-cooled reactor

Matsuura, Hideaki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki

no journal, , 

JAEA and Kyushu University have studied the tritium production method using high temperature gas-cooled reactors (HTGR) for initial fusion reactors. In this method, lithium compounds are loaded into the reactor core and tritium is produced with $$^{6}$$Li(n,a)T reaction. We studied about the optimization of a lithium loading method, an effective tritium containment method and the nuclear thermal design of a lithium loaded HTGR, and consequently we confirmed the feasibility of the tritium production method. This paper describes the overview of the study.

Oral presentation

Current study and future progress for tritium production method using high temperature gas cooled reactor, 2; Study on tritium production and confinement in high-temperature gas-cooled reactor

Katayama, Kazunari*; Matsuura, Hideaki*; Otsuka, Teppei*; Fukada, Satoshi*; Goto, Minoru; Nakagawa, Shigeaki

no journal, , 

JAEA and Kyushu University have studied the tritium production method using high temperature gas-cooled reactors (HTGR) for initial fusion reactors. In this method, lithium compounds are loaded into the reactor core and tritium is produced with $$^{6}$$Li(n,a)T reaction. We studied about the optimization of a lithium loading method, an effective tritium containment method and the nuclear thermal design of a lithium loaded HTGR, and consequently we confirmed the feasibility of the tritium production method. This paper describes the results of the hydrogen permeation experiment and the results of the tritium permeation analysis based on the obtained data from the experiments.

Oral presentation

Study on lithium rod test module and irradiation method of tritium production using high temperature gas-cooled reactor; Evaluation of test module with Zr layer

Ida, Yuma*; Matsuura, Hideaki*; Nagasumi, Satoru*; Koga, Yuki*; Okamoto, Ryo*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo

no journal, , 

Tritium production method using HTGRs (High Temperature Gas-cooled reactors) is studied as the tritium supplying method for initial D-T fusion reactors. In this method, tritium is produced by $$^{6}$$Li (n,$$alpha$$)T reaction. The amount of tritium production and the tritium confinement capability were evaluated in case of the irradiation capsule including the Li compound is installed into the HTGRs in the past. In this study, the tritium confinement capability is evaluated for the irradiation capsule with ZrC layer by performing calculations of the amount of tritium leakage. The calculation results showed that the amount of tritium leakage is decreased to one fifth with the ZrC layer.

Oral presentation

R&D of advanced stainless steels for BWR fuel claddings, 2-6; Tritium permeability and high temperature steam oxidation properties

Takahashi, Katsuhito*; Sakamoto, Kan*; Otsuka, Teppei*; Ukai, Shigeharu*; Hirai, Mutsumi*; Yamashita, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

Study on tritium confinement method using Li rod with Zr in very high temperature gas-cooled reactor; Hydrogen storage properties of Zr in high temperature (700$$sim$$850$$^{circ}$$C) conditions

Okamoto, Ryo*; Matsuura, Hideaki*; Ida, Yuma*; Koga, Yuki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; Nagasumi, Satoru; et al.

no journal, , 

Currently, many researches to achieve DT nuclear-fusion power generation are under proceeding but the method to provide initial tritium loaded to fusion prototype reactor is not clear. The method of tritium production by using high temperature gas-cooled reactor (HTGR) was proposed. In this method, lithium rods are loaded to the reactor core of HTGR and tritium is produced by $$^{6}$$Li(n,$$alpha$$)T reaction. And the method to reduce the spilled tritium by using the lithium rod with zirconium layer was proposed. In this study, the experiments to evaluate the performance of hydrogen absorption in the zirconium layer were conducted under the temperature condition more than 700$$^{circ}$$C which is the normal operation condition for the very high temperature gas-cooled reactor (VHTR). The experimental result concerning solubility and diffusion factor of hydrogen in the zirconium layer will be presented and discussed.

Oral presentation

The Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor

Ida, Yuma*; Matsuura, Hideaki*; Nagasumi, Satoru; Okamoto, Ryo*; Koga, Yuki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; et al.

no journal, , 

Large quantity of tritium is demanded for starting up of fusion reactor and engineering test using tritium for fusion blanket system. However, tritium is very rare and kg order of tritium must be produced artificially. Tritium production, by $$^{6}$$Li(n,$$alpha$$)T reaction using the high temperature gas-cooled reactor (HTGR), has been proposed. In this method, loading of Li rods into burnable poison (BP) holes in HTGR is considered. In this paper, the Li rod suited to the demand for the utilization in High Temperature engineering Test Reactor (HTTR) is designed, and tritium production and leakage from Li-rod capsule are evaluated by adjusting the thickness of LiAlO$$_{2}$$, alumina, and Zr layers. A scenario of irradiation test supposed to be conducted at HTTR for demonstration of the tritium production and containment performance of the Li rod is presented.

Oral presentation

Study on tritium confinement method using Li rod with Zr in HTGR; Hydrogen absorption properties of Zr in high temperature (700-900$$^{circ}$$C) conditions

Okamoto, Ryo*; Matsuura, Hideaki*; Ida, Yuma*; Koga, Yuki*; Suganuma, Takuro*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; et al.

no journal, , 

It has been proposed that lithium rods, which are cylindrical lithium compounds, are loaded into a HTGR and tritium for initial fusion reactors is produced by $$^{6}$$Li(n,$$alpha$$)T reaction. In this study, it was discussed that the lithium rods are covered with zirconium layers to prevent the produced tritium leak. The solubility and diffusion coefficient of hydrogen in zirconium were measured and the effectiveness of the zirconium layers on prevention of tritium leakage was estimated with the measured values. As a result, the tritium leakage ratio with the zirconium layers was estimated two orders lower than that without the zirconium layers, and hence it was considered that the zirconium layer is very effective on the prevention of the tritium leakage.

Oral presentation

Study on hydrogen permeation behavior in PyC coated graphite

Suematsu, Senri*; Katayama, Kazunari*; Izumino, Junichi*; Matsuura, Hideaki*; Otsuka, Teppei*; Fukada, Satoshi*; Goto, Minoru; Nakagawa, Shigeaki

no journal, , 

It has been proposed that lithium compounds are loaded into a HTGR and tritium for initial fusion reactors is produced by $$^{6}$$Li(n,$$alpha$$)T reaction. Coating PyC layer on the lithium compounds could be one of the method for preventing the produced tritium leakage. In this study, hydrogen permeation experiment was performed to obtain tritium transmission coefficient in PyC, which is an important value to estimate the amount of the tritium leakage.

Oral presentation

Study on lithium rod module and irradiation method for tritium production using high temperature gas-cooled reactor

Koga, Yuki*; Matsuura, Hideaki*; Okamoto, Ryo*; Ida, Yuma*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; Nagasumi, Satoru; et al.

no journal, , 

Large quantity of tritium is demanded for starting up of fusion reactor and engineering test using tritium for fusion blanket system. Tritium production, by $$^{6}$$Li(n, $$alpha$$)T reaction using the high temperature gas-cooled reactor (HTGR), has been proposed and the method to produce tritium by loading the lithium rods as burnable poison in the reactor core has been studied. In this presentation, the design of lithium rods to be loaded to High Temperature engineering Test Reactor (HTTR) and its irradiation test plan to demonstrate tritium production are presented.

Oral presentation

The Influence of hydrogen absorption performance of Zr on tritium confinement properties of Li rod in HTGR

Okamoto, Ryo*; Matsuura, Hideaki*; Ida, Yuma*; Koga, Yuki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; Nagasumi, Satoru

no journal, , 

A study on tritium production using a high-temperature gas-cooled reactor has been carried out and it was proposed that zirconium is loaded into the lithium irradiation capsule to confine tritium within the irradiation capsule under high temperature condition. In this study, zirconium loading method was examined by numerical calculations to improve the tritium confinement. As a result, it was found that improvement in the tritium confinement can be expected by loading spherical zirconium into the irradiation capsule.

Oral presentation

Deuterium absorption properties of Zr in Li rod for high temperature gas-cooled reactor

Suganuma, Takuro*; Matsuura, Hideaki*; Okamoto, Ryo*; Koga, Yuki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Tobita, Kenji*

no journal, , 

A study on the confinement of tritium, which is a fuel for fusion reactors and is produced by a HTGR, has been conducted for high temperature condition. The tritium is confined in the irradiation capsule with a zirconium layer. The relation between a H/Zr ratio and an apparent diffusion coefficient of tritium in the zirconium layer is needed to evaluate the tritium confinement performance of the irradiation capsule. This relation was examined with a experiment using deuteron. As a result, the apparent diffusion coefficient deceases with an increase of the H/Zr ratio. This phenomena should be caused by a generation of hydrogen. After that, the analysis for an amount of the release of the tritium from the irradiation capsule will be calculated using obtained data to evaluate the containment performance of the irradiation capsule.

Oral presentation

Study on the structure of Li rod using Zr particles for T-production in HTGR; Non-equilibrium Hydrogen absorption properties of Zr

Okamoto, Ryo*; Matsuura, Hideaki*; Koga, Yuki*; Suganuma, Takuro*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; Tobita, Kenji*

no journal, , 

Currently, the method to reduce the spilled tritium by using the lithium rod with zirconium layer under the high temperature condition was proposed in the study of the tritium production by using high temperature gas-cooled reactor (HTGR). In this study, the experiments to evaluate the performance of hydrogen absorption in the zirconium layer were conducted. The experimental result concerning hydrogen absorption properties of zirconium will be presented and discussed.

Oral presentation

Study on the Li loading rod irradiation test and granular Zr performance evaluation method using the HTTR

Koga, Yuki*; Matsuura, Hideaki*; Okamoto, Ryo*; Suganuma, Takuro*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; Tobita, Kenji*

no journal, , 

Production of tritium using a high temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, Li-loading rods are installed at the moderator region of the HTGR. The tritium retention capability of Li-loading rod would decline due to high temperature condition from 1100K to 1200K during HTGR rated power operation. Therefore, the zirconium is employed as tritium absorber which is granular and is coated with nickel to prevent from declining the tritium absorption capability due to zirconium oxidation and so on. In this presentation, the design concept of Li-loading rods with granular zirconium coated with nickel and the method of irradiation test by using the HTTR which is a test reactor of HTGR are presented.

Oral presentation

Li nuclear heat generation in the HTGR for T production and effect on T containment performance

Koga, Yuki*; Matsuura, Hideaki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Hamamoto, Shimpei; Ishitsuka, Etsuo; Nakagawa, Shigeaki; Tobita, Kenji*

no journal, , 

The tritium confinement performance of the designed irradiation capsule was evaluated for the case where tritium was produced by loading Li compound into GTHTR300. Calculation of tritium outflow from the irradiation capsule was performed taking into account the nuclear heat generation of the $$^{6}$$Li(n,$$alpha$$)T reaction in addition to the core temperature. As a result, by taking into account nuclear heat, the outflow of T was reduced by 15% from the previous calculation results, and the confinement performance was improved.

Oral presentation

Study on T-production Li rod for high temperature gas cooled reactor; Temperature dependence of the hydrogen absorption speed in Zr

Nakagawa, Kyoichi*; Matsuura, Hideaki*; Koga, Yuki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Hamamoto, Shimpei; Ishitsuka, Etsuo; Nakagawa, Shigeaki; Tobita, Kenji*; et al.

no journal, , 

The containment of tritium by using zirconium in the lithium rod applied to the tritium production in the HTGR has been investigated. Considering the temperature distribution on the reactor core, the containment performance to tritium was evaluated through the measurement of the Zr hydrogen absorption rate in its temperature range.

Oral presentation

Study on T production using high-temperature gas-cooled reactor for fusion reactors, 4; Feasibility study on irradiation test for tritium production capsule

Ishitsuka, Etsuo; Ho, H. Q.; Shimazaki, Yosuke; Nakagawa, Shigeaki; Goto, Minoru; Matsuura, Hideaki*; Otsuka, Teppei*; Katayama, Kazunari*; Iigaki, Kazuhiko

no journal, , 

As part of the development of tritium production using a high-temperature gas-cooled reactor for the initial loading of a fusion reactor, an irradiation test of a tritium production capsule has been studied. In this presentation, a feasibility study on irradiation test using JRR-3 will be introduced.

Oral presentation

Study on tritium production using high-temperature gas-cooled reactor for fusion reactors; Structure of the irradiation test module and experimental method

Kitagawa, Kanta*; Matsuura, Hideaki*; Kawai, Hitomi*; Katayama, Kazunari*; Otsuka, Teppei*; Ishitsuka, Etsuo; Nakagawa, Shigeaki; Goto, Minoru*; Tobita, Kenji*; Konishi, Satoshi*; et al.

no journal, , 

Tritium production using a high temperature gas cooled reactor has been studied to get for the start-up of an initial DEMO fusion reactor and for technical testing of related tritium circulation systems. The characteristics of hydrogen absorption in the case of change from room temperature to high temperature for zirconium particle with nickel coating was obtained and investigated the analytical simulation model. And the configuration (for example, the numbers of zirconium particle with nickel coating and the amount of LiAlO$$_{2}$$) of test specimen for irradiation test and the test method were discussed.

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